======================================================================= Activate

Activate

PROGRAM ACTIVATE Activate

VERS. 2000-1 (APRIL 2000) *INITIAL VERSION. Activate

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Activate

VERS. 2004-1 (JAN. 2004) *CORRECTED ERROR - FIRST RECORD AFTER Activate

MF=10 WAS MISSING. Activate

*ADDED INCLUDE TO DEFINE COMMON Activate

*INCREASED MAX. POINTS FROM 100,000 Activate

TO 1,000,000. Activate

Activate

Acknowledgement 2004 Activate

-------------------- Activate

Currently almost all improvements to this code are based upon Activate

feedback from code users who report problems. This feedback Activate

benefits ALL users of this code, and ALL users are encouraged Activate

to report problems. Activate

Activate

Improvements on the 2004 version of this code based on user Activate

feedback including, Activate

1) Andrej Trkov - reported that the first record of the section Activate

after an inserted MF=10 was missing. Activate

Activate

OWNED, MAINTAINED AND DISTRIBUTED BY Activate

------------------------------------ Activate

THE NUCLEAR DATA SECTION Activate

INTERNATIONAL ATOMIC ENERGY AGENCY Activate

P.O. BOX 100 Activate

A-1400, VIENNA, AUSTRIA Activate

EUROPE Activate

Activate

ORIGINALLY WRITTEN BY Activate

------------------------------------ Activate

DERMOTT E. CULLEN Activate

UNIVERSITY OF CALIFORNIA Activate

LAWRENCE LIVERMORE NATIONAL LABORATORY Activate

L-159 Activate

P.O. BOX 808 Activate

LIVERMORE, CA 94550 Activate

U.S.A. Activate

TELEPHONE 925-423-7359 Activate

E. MAIL CULLEN1@LLNL.GOV Activate

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Activate

Activate

AUTHORS MESSAGE Activate

--------------- Activate

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Activate

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Activate

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Activate

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION. Activate

Activate

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Activate

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Activate

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Activate

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Activate

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Activate

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Activate

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Activate

COMPUTER. Activate

Activate

PURPOSE Activate

------- Activate

THIS PROGRAM IS DESIGNED TO CREATE FILE 10 ACTIVATION CROSS Activate

SECTIONS BY COMBINING FILE 3 CROSS SECTIONS AND FILE 9 MULTIPLIERS Activate

Activate

IN THE FOLLOWING DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY Activate

---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE Activate

TAPE, CARDS, DISK OR ANY OTHER MEDIUM. Activate

Activate

ASSUMPTIONS Activate

----------- Activate

IT IS ASSUMED THAT THE FILE 3 AND 9 DATA HAVE BEEN LINEARIZED Activate

BEFORE THIS CODE IS USED - FILE 3 AND 9 DATA CAN BE LINEARIZED Activate

USING PROGRAM LINEAR. Activate

Activate

IT IS ASSUMED THAT THE FILE 9 MULTIPLIERS ARE FAIRLY SMOOTH VERSUS Activate

ENERGY, AND THAT THE ACTIVATION CROSS SECTIONS FOR FILE 10 CAN BE Activate

DEFINED AT EXACTLY THE SAME ENERGIES AS THE FILE 3 CROSS SECTIONS, Activate

AND THAT THESE NEED MERELY BE MULTIPLIED BY THE FILE 9 TO DEFINE Activate

THE FILE 10 ACTIVATION CROSS SECTIONS. Activate

Activate

ENDF/B FORMAT Activate

------------- Activate

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Activate

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Activate

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Activate

Activate

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Activate

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Activate

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Activate

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Activate

CORRECTLY OUTPUT ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451 Activate

AND ALL SECTIONS OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL Activate

OTHER SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO Activate

THE CORRECTNESS OR INCORRECTNESS OF ALL OTHER SECTIONS. Activate

Activate

OUTPUT FORMAT Activate

------------- Activate

ALL ENERGIES WILL BE OUTPUT IN F (INSTEAD OF E) FORMAT IN ORDER Activate

TO ALLOW ENERGIES TO BE WRITTEN WITH UP TO 9 DIGITS OF ACCURACY. Activate

COMPARISON OF THE NORMAL ENDF/B CONVENTION OF 6 DIGITS TO THE 9 Activate

DIGIT OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE TO USE Activate

THE 9 DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA DUE TO Activate

TRUNCATION OF ENERGIES TO 6 DIGITS DURING OUTPUT. Activate

Activate

CONTENTS OF OUTPUT Activate

------------------ Activate

ENTIRE EVALUATIONS ARE OUTPUT, NOT JUST THE PROCESSED DATA, E.G., Activate

ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO INCLUDED. Activate

Activate

DOCUMENTATION Activate

------------- Activate

THE FACT THAT THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED Activate

BY THE ADDITION OF 3 COMMENT LINES AT THE END OF EACH HOLLERITH Activate

SECTION IN THE FORM Activate

Activate

***************** PROGRAM ACTIVATE (2004-1) **************** Activate

FILE 10 ACTIVATION CROSS SECTIONS HAVE BEEN DEFINED BY COMBINING Activate

FILE 3 CROSS SECTIONS AND FILE 9 MULTIPLIERS. FILE 9 DELETED. Activate

Activate

THE ORDER OF SIMILAR COMMENTS (FROM RECENT, SIGMA1 AND GROUPIE) Activate

REPRESENTS A COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON Activate

THE DATA BY THESE PROGRAMS. Activate

Activate

THESE COMMENT LINES ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Activate

I.E., THIS PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Activate

OF THE HOLLERITH SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF Activate

EARLIER VERSIONS OF ENDF/B. BY READING AN EXISTING MF=1, MT=451 Activate

IT IS POSSIBLE FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF Activate

THE ENDF/B FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF Activate

MF=1, MT=451 PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO Activate

DETERMINE WHICH VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND Activate

AS SUCH IT IS IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT Activate

SHOULD BE USED TO CREATE A HOLLERITH SECTION. Activate

Activate

REACTION INDEX Activate

-------------- Activate

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Activate

SECTION MF=1, MT=451 OF EACH EVALUATION. Activate

Activate

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Activate

THIS CONVENTION HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT Activate

REQUIRE A CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Activate

NOT CONSIDERED WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING Activate

A CORRECT REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE Activate

A REACTION INDEX FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Activate

YOU MAY USE PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX. Activate

Activate

SECTION SIZE Activate

------------ Activate

SECTIONS OF MF=9 MULTIPLIERS ARE LIMITED TO A MAXIMUM OF 10,000 Activate

ENERGY POINTS. Activate

Activate

THERE IS NO LIMIT ON THE NUMBER OF ENERGY POINTS IN MF=3 AND 10 Activate

TABLES. Activate

Activate

SELECTION OF DATA Activate

----------------- Activate

THE PROGRAM PROCESSES ALL ENDF/B DATA ON A SERIES OF ENDF/B TAPES. Activate

Activate

PROGRAM OPERATION Activate

----------------- Activate

PASS #1 Activate

------- Activate

THE ENTIRE MAT IS COPIED TO A SCRATCH FILE IN THE ENDF/B ASCII Activate

FORMAT AND WHILE COPYING IT TO SCRATCH MF=3, 9, AND 10 ARE ALSO Activate

COPIED TO SEPERATE SCRATCH FILES, I.E., THERE ARE A TOTAL OF 4 Activate

SCRATCH FILES - SEE THEIR DEFINITIONS BELOW. Activate

Activate

PASS #2 Activate

------- Activate

IF NO MF=9 MULTIPLIERS ARE FOUND DURING PASS #1, THE ENTIRE MAT Activate

IS COPIED FROM SCRATCH TO THE OUTPUT FILE, WITHOUT ANY CHECKS. Activate

Activate

IF MF=9 MULTIPLIERS ARE FOUND THEY ARE USED WITH MF=3 CROSS Activate

SECTIONS TO CREATE MF=10 ACTIVATION CROSS SECTIONS. Activate

Activate

FOR ANY SECTION OF MF=10 DATA FOR WHICH NO MF=9 MULTIPLIERS ARE Activate

FOUND, THE ORIGINAL MF=10 IS OUTPUT. Activate

Activate

FOR CONSISTENCY ALL MF=9 MULTIPLIERS ARE DELETED, I.E., THEY ARE Activate

NOT INCLUDED IN THE OUTPUT. Activate

Activate

KEEP EVALUATED DATA POINTS Activate

-------------------------- Activate

THE FILE 10 OUTPUT WILL BE AT EXACTLY THE SAME ENERGY POINTS AS Activate

THE FILE 3 CROSS SECTIONS USED TO DEFINE THE FILE 10 ACTIVATION Activate

CROSS SECTIONS. Activate

Activate

INPUT FILES Activate

----------- Activate

UNIT DESCRIPTION Activate

---- ----------- Activate

2 INPUT LINES (BCD - 80 CHARACTERS/RECORD) Activate

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Activate

Activate

OUTPUT FILES Activate

------------ Activate

UNIT DESCRIPTION Activate

---- ----------- Activate

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Activate

11 FINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Activate

Activate

SCRATCH FILES Activate

------------- Activate

UNIT DESCRIPTION Activate

---- ----------- Activate

12 SCRATCH FILE FOR ALL MAT (BCD - 80 CHARACTERS/RECORD) Activate

14 SCRATCH FILE FOR MF=3 DATA (BCD - 80 CHARACTERS/RECORD) Activate

15 SCRATCH FILE FOR MF=9 DATA (BCD - 80 CHARACTERS/RECORD) Activate

16 SCRATCH FILE FOR MF=10 DATA (BCD - 80 CHARACTERS/RECORD) Activate

Activate

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILEIO) Activate

---------------------------------------------------- Activate

UNIT FILE NAME Activate

---- ---------- Activate

2 ACTIVATE.INP Activate

3 ACTIVATE.LST Activate

10 ENDFB.IN Activate

11 ENDFB.OUT Activate

12 (SCRATCH) Activate

14 (SCRATCH) Activate

15 (SCRATCH) Activate

Activate

INPUT PARAMETERS Activate

---------------- Activate

Activate

LINE COLS. DESCRIPTION Activate

---- ----- ----------- Activate

1 1-60 ENDF/B INPUT DATA FILENAME Activate

(STANDARD OPTION = ENDFB.IN) Activate

2 1-60 ENDF/B OUTPUT DATA FILENAME Activate

(STANDARD OPTION = ENDFB.OUT) Activate

Activate

ANY NUMBER OF PAIRS OF INPUT LINES MAY BE USED, TO PROCESS ANY Activate

NUMBER OF ENDF/B TAPES, ONE AFTER ANOTHER. Activate

Activate

EXAMPLE INPUT NO. 1 Activate

------------------- Activate

PROCESS ENDF/B TAPES NAMED, TAPE121, TAPE122, AND TAPE123, AND Activate

NAME THE OUTPUT FILES ACTIVATE121, ACTIVATE122, AND ACTIVATE123. Activate

Activate

IN THIS CASE THE FOLLOWING 6 INPUT LINES ARE REQUIRED Activate

Activate

TAPE121 Activate

ACTIVATE121 Activate

TAPE122 Activate

ACTIVATE122 Activate

TAPE123 Activate

ACTIVATE123 Activate

Activate

EXAMPLE INPUT NO. 2 Activate

------------------- Activate

SAME AS THE ABOVE CASE, EXCEPT THAT IN THIS CASE THE ORIGINAL Activate

3 TAPES ARE IN A DIRECTORY NAMED \ENDFB6\ORIGINAL, AND THE Activate

RESULTS WILL BE WRITTEN INTO A DIRECTORY NAMED \ENDFB6\ACTIVATE. Activate

Activate

IN THIS CASE THE FOLLOWING 6 INPUT LINES ARE REQUIRED Activate

Activate

\ENDFB6\ORIGINAL\TAPE121 Activate

\ENDFB6\ACTIVATE\ACTIVATE121 Activate

\ENDFB6\ORIGINAL\TAPE122 Activate

\ENDFB6\ACTIVATE\ACTIVATE122 Activate

\ENDFB6\ORIGINAL\TAPE123 Activate

\ENDFB6\ACTIVATE\ACTIVATE123 Activate

Activate

======================================================================= Activate

======================================================================= Complot

Complot

PROGRAM COMPLOT Complot

=============== Complot

VERSION 83-1 (FEBRUARY, 1983) Complot

VERSION 83-2 (MAY, 1983) Complot

VERSION 83-3 (DECEMBER, 1983) *MAJOR MODIFICATION. Complot

*ADDED SELECTION OF PLOTS BY MAT OR Complot

ZA/MT/ENERGY RANGE (EV). Complot

*ADDED VARIABLE AXIS UNITS (PROGRAM Complot

CONTROLLED..X=MILLI-EV, EV, KEV, Complot

MEV...Y=MILLI-BARNS, BARNS). Complot

VERSION 84-1 (APRIL, 1984) *ADDED SELECTION BY REACTION/ENERGY Complot

RANGE. Complot

*ADDED IDENTIFY DATA POINTS OPTION Complot

(SMALL BOX DRAWN AROUND EACH CROSS Complot

SECTION AND RATIO POINT). Complot

*IMPROVED NON-IBM GRAPHICS INTERFACE Complot

(ALL CHARACTER POSITIONING NOW Complot

BASED ON CHARACTER, NOT RASTER, Complot

SIZE). Complot

VERSION 85-1 (APRIL, 1985) *SPECIAL I/O ROUTINES TO GUARANTEE Complot

ACCURACY OF ENERGY. Complot

*DOUBLE PRECISION TREATMENT OF Complot

ENERGY (REQUIRED FOR NARROW Complot

RESONANCES). Complot

*ADDED (ZA,MT) EQUIVALENCE OPTION. Complot

*ADDED SMALL PLOT OPTION. Complot

VERSION 85-2 (AUGUST, 1985) *FORTRAN-77/H VERSION Complot

VERSION 86-1 (JANUARY, 1986) *ENERGY DEPENDENT SCATTERING RADIUS Complot

VERSION 86-2 (DECEMBER, 1986) *DOUBLE PRECISION PLOT SCALING Complot

(REQUIRED FOR NARROW ENERGY RANGES) Complot

VERSION 88-1 (JULY 1988) *MAJOR REVISION TO MAKE CODE EASILY Complot

INTERFACEABLE TO ALMOST ANY PLOTTER Complot

*WARNING..INPUT PARAMETERS FROM BEEN Complot

CHANGED (SEE, DESCRIPTION BELOW) Complot

*COMPUTER INDEPENDENT SOFTWARE Complot

CHARACTERS. Complot

*COLOR PLOTS. Complot

*MT NUMBER DEFINITIONS FROM DATA Complot

FILE READ BY PROGRAM Complot

*FORTRAN-77 REQUIRED (FORTRAN-H NO Complot

SUPPORTED BY THIS PROGRAM). Complot

*OPTION...INTERNALLY DEFINE ALL I/O Complot

FILE NAMES (SEE, SUBROUTINE FILEIO Complot

FOR DETAILS). Complot

*IMPROVED BASED ON USER COMMENTS. Complot

VERSION 88-2 (OCTOBER 1988) *IMPROVED BASED ON USER COMMENTS. Complot

*ADDED LIVERMORE CIVIC COMPILER Complot

CONVENTIONS. Complot

*UPDATED TO USE NEW PROGRAM CONVERT Complot

KEYWORDS. Complot

VERSION 89-1 (JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO Complot

INSURE PROGRAM WILL NOT DO ANYTHING Complot

CRAZY. Complot

*FORTRAN-77/FORTRAN-H COMPATIBLE Complot

*SPECIAL ENDF/B MATERIAL DEFINITIONS Complot

(ZA.LT.1000) FROM DATA FILE READ Complot

BY PROGRAM. Complot

VERSION 89-2 (MARCH 1989) *ADDED ENDF/B-V AND VI MT Complot

DEFINITIONS. PROGRAM WILL DETERMINE Complot

ENDF/B FORMAT BASED ON MF=1, Complot

MT=451 AND USE AS PPROPRIATE MT Complot

DEFINITIONS. IF NO MF=1, MT=451 Complot

PROGRAM WILL USE ENDF/B-VI Complot

MT DEFINITIONS. Complot

VERSION 90-1 (AUGUST 1990) *A NEW PROGRAM Complot

*ADDED INTERACTIVE MOUSE INPUT Complot

*ADDED 3 CHARACTER FONTS Complot

*ADDED PHOTON DATA, MF=23 AND 27 Complot

*ADDED FORTRAN SAVE OPTION. Complot

*ADDED MAXIMUM RATIO RANGE WHEN Complot

PLOTTING RATIOS. Complot

*ADDED GRID TYPES Complot

*ADDED VARIABLE LINE THICKNESS Complot

*WARNING...INPUT PARAMETER FORMAT Complot

HAS BEEN CHANGED...SEE DESCRIPTION Complot

BELOW. Complot

VERSION 92-1 (JANUARY 1992) *ADDED INCIDENT CHARGED PARTICLES Complot

(IDENTIFIED IN PLOT TITLES) Complot

*ADDED COMPLETELY COMPATIBLE I/O Complot

FOR READING FLOATING POINT NUMBERS. Complot

VERSION 92-2 (MAY 1992) *CORRECTED DESCRIPTION OF INPUT Complot

PARAMETERS AND EXAMPLE PROBLEMS. Complot

*ADDED VARIABLE CHARACTER SIZE INPUT Complot

VERSION 93-1 (MARCH 1993) *UPDATE FOR ON SCREEN GRAPHIC Complot

OUTPUT USING THE LAHEY COMPILER Complot

*ADDED NU-BAR (TOTAL, DELAYED, Complot

PROMPT). Complot

VERSION 94-1 (JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES Complot

TO ALLOW ACCESS TO FILE STRUCTURES Complot

(WARNING - INPUT PARAMETER FORMAT Complot

HAS BEEN CHANGED) Complot

*CLOSE ALL FILES BEFORE TERMINATING Complot

(SEE, SUBROUTINE ENDIT) Complot

VERSION 95-1 (MARCH 1995) *CORRECTED CROSS SECTION Complot

MULTIPLIER FOR EQUIVALENCES Complot

*CORRECTED RATIO SCALING, FOR Complot

MAXIMUM RATIO LESS THAN 1.0 Complot

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Complot

*IMPROVED COMPUTER INDEPENDENCE Complot

*ALL DOUBLE PRECISION Complot

*UNIFORM TREATMENT OF ENDF/B I/O Complot

*IMPROVED OUTPUT PRECISION Complot

*DEFINED SCRATCH FILE NAMES Complot

*INCREASED PAGE SIZE FROM 24000 Complot

TO 48000 POINTS Complot

VERSION 97-1 (APRIL 1997) *INCREASED PAGE SIZE FROM 48000 Complot

TO 480000 POINTS Complot

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Complot

POINT READ FOR MORE DIGITS Complot

*UPDATED TEST FOR ENDF/B FORMAT Complot

VERSION BASED ON RECENT FORMAT CHANGE Complot

*GENERAL IMPROVEMENTS BASED ON Complot

USER FEEDBACK Complot

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Complot

USER FEEDBACK Complot

VERS. 2002-1 (MAY 2002) *INPUT PARAMETERS OPTIONAL Complot

*CONTROL MINIMUM RATIO RANGE BY INPUT Complot

*OPTIONAL BLACK OR WHITE BACKGROUND Complot

VERS. 2004-1 (SEPT. 2004) *ADDED INCLUDE FOR COMMON Complot

*INCREASED PAGE SIZE FROM 480000 Complot

TO 600000 POINTS Complot

*ADDED NEW REICH-MOORE TO FILE2 TO Complot

ALLOW IDENTIFICATION OF RESOLVED AND Complot

ANY FOLLOWING UNRESOLVED RESONANCE Complot

REGIONS. Complot

Complot

OWNED, MAINTAINED AND DISTRIBUTED BY Complot

------------------------------------ Complot

THE NUCLEAR DATA SECTION Complot

INTERNATIONAL ATOMIC ENERGY AGENCY Complot

P.O. BOX 100 Complot

A-1400, VIENNA, AUSTRIA Complot

EUROPE Complot

Complot

ORIGINALLY WRITTEN BY Complot

------------------------------------ Complot

DERMOTT E. CULLEN Complot

UNIVERSITY OF CALIFORNIA Complot

LAWRENCE LIVERMORE NATIONAL LABORATORY Complot

L-159 Complot

P.O. BOX 808 Complot

LIVERMORE, CA 94550 Complot

U.S.A. Complot

TELEPHONE 925-423-7359 Complot

E. MAIL CULLEN1@LLNL.GOV Complot

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Complot

Complot

Complot

AUTHORS MESSAGE Complot

--------------- Complot

THE COMMENTS BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION Complot

ALL RECENT IMPROVEMENTS. PLEASE READ ALL OF THESE COMMENTS BEFORE, Complot

PARTICULARLY THE COMMENTS CONCERNING MACHINE DEPENDENT CODING. Complot

Complot

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Complot

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Complot

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Complot

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Complot

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Complot

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Complot

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Complot

COMPUTER. Complot

Complot

PURPOSE Complot

------- Complot

COMPARE ENDF/B FORMATTED DATA FROM TWO SEPARATE INPUT TAPES. Complot

REACTIONS ARE CONSIDERED TO BE COMPARABLE IF THEY HAVE THE SAME Complot

(ZA,MF,MT). RESULTS ARE PRESENTED IN GRAPHICAL FORM. Complot

Complot

IN THE FOLLOWING FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B Complot

TAPE--WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS, Complot

DISK OR ANY OTHER MEDIUM. Complot

Complot

ON WHAT COMPUTERS WILL THE PROGRAM RUN Complot

------------------------------------------------------------------ Complot

THE PROGRAM HAS BEEN IMPLEMENTED ON A VARIETY OF COMPUTERS FROM Complot

CRAY AND IBM MAINFRAME TO SUN WORKSTATIONS TO AN IBM-AT PC. THE Complot

PROGRAM IS SMALL ENOUGH TO RUN ON VIRTUALLY ANY COMPUTER. Complot

Complot

THE PROGRAM USES A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE Complot

(DESCRIBED BELOW) AND ALLOWS THE USER SPECIFY THE PHYSICAL SIZE Complot

OF THE PLOTTER BEING USED, BY INPUT PARAMETERS. USING THESE Complot

CONVENTIONS THIS PROGRAM CAN BE EASILY INTERFACED TO VIRTUALLY Complot

ANY PLOTTER. Complot

Complot

FOR SPECIAL CONSIDERATIONS SEE THE SECTIONS BELOW ON, Complot

(1) COMPUTER DEPENDENT CODING Complot

(2) PLOTTER/GRAPHICS TERMINAL INTERFACE Complot

Complot

GRAPHICS INTERFACE Complot

------------------------------------------------------------------ Complot

THIS PROGRAM USES A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE WHICH Complot

REQUIRES ONLY 3 SUBROUTINES...PLOTS, PLOT AND PEN (DESCRIBED IN Complot

DETAIL BELOW). ALL CHARACTERS AND SYMBOLS ARE DRAWN USING TABLES Complot

OF PEN STROKES (SUPPLIED WITH THIS PROGRAM). USING THIS METHOD Complot

THE PROGRAM SHOULD BE SIMPLE TO INTERFACE TO VIRTUALLY ANY PLOTTER Complot

OR GRAPHICS TERMINAL AND THE APPEARANCE AND LAYOUT OF THE PLOTS Complot

SHOULD BE INDEPENDENT OF WHICH PLOTTER IS USED. Complot

Complot

ON WHAT PLOTTERS WILL THE PROGRAM RUN Complot

------------------------------------------------------------------ Complot

THE PLOTTER MAY USE UNITS OF INCHES, CENTIMETERS, MILLIMETERS, Complot

VIRTUALLY ANYTHING. INTERNALLY THE PROGRAM WILL DEFINE PLOTS IN Complot

APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. AS PART OF THE Complot

INPUT THE USER DEFINES THE ACTUAL SIZE OF THE PLOT IN THE UNITS Complot

(I.E., INCHES, CENTIMETERS, MILLIMETERS, WHATEVER) OF THE REAL Complot

PLOT. THE PLOT IS TRANSFORMED TO THE SIZE OF THE LOCAL PLOTTER Complot

AND OUTPUT. USING THIS CONVENTION THIS PROGRAM SHOULD BE EASY Complot

TO INTERFACE TO VIRTUALLY ANY PLOTTER OR GRAPHICS TERMINAL. Complot

Complot

PROGRAM IDENTIFICATION Complot

---------------------- Complot

AS DISTRIBUTED THE FIRST FRAME OF PLOTTED OUTPUT WILL DOCUMENT Complot

THE PROGRAM NAME, VERSION AND INSTALLATION. THIS INFORMATION IS Complot

STORED AS DATA IN THE ARRAY VERSES NEAR THE BEGINNING OF Complot

SUBROUTINE FRAME1. IF YOU WISH TO CUSTOMIZE THE OUTPUT TO IDENTIFY Complot

YOUR INSTALLATION CHANGE THE LAST TWO LINES OF THE ARRAY (VERSES). Complot

Complot

ENDF/B FORMAT Complot

------------- Complot

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Complot

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Complot

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Complot

Complot

BOTH SETS OF EVALUATED DATA MUST BE IN THE ENDF/B FORMAT. ONLY Complot

SECTIONS OF FILE 2 (RESONANCE PARAMETERS) AND FILES 3, 23 AND 27 Complot

(TABULATED DATA) WILL BE READ AND ALL OTHER SECTIONS WILL BE Complot

SKIPPED. IN FILE 2 THE ONLY IMPORTANT INFORMATION IS THE ENERGY Complot

LIMITS OF THE RESOLVED AND UNRESOLVED RESONANCE REGION WHICH IS Complot

LOCATED IN THE SAME FIELDS IN ALL VERSIONS OF THE ENDF/B FORMAT. Complot

SIMILARLY THE FORMAT OF FILES 3, 23 AND 27 IS THE SAME IN ALL Complot

VERSIONS OF ENDF/B. THEREFORE THIS PROGRAM CAN BE USED WITH DATA Complot

IN ANY ENDF/B FORMAT (I.E. ENDF/B-I, II, III, IV, V OR VI). Complot

Complot

CROSS SECTION INTERPOLATION Complot

--------------------------- Complot

CROSS SECTIONS MUST BE IN EITHER HISTOGRAM (I.E., INTERPOLATION Complot

LAW 1) OR LINEARLY INTERPOLABLE (I.E. INTERPOLATION LAW 2) FORM. Complot

IF THEY ARE NOT A WARNING MESSAGE WILL BE PRINTED AND EXECUTION Complot

WILL BE TERMINATED. SEE INSTRUCTIONS BELOW ON HOW TO CONVERT Complot

DATA TO HISTOGRAM OR LINEARLY INTERPOLABLE FORM. Complot

Complot

REACTION INDEX Complot

-------------- Complot

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Complot

SECTION MF=1, MT=451 OF EACH EVALUATION. Complot

Complot

SECTION SIZE Complot

------------ Complot

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Complot

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Complot

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Complot

Complot

DATA SELECTION Complot

-------------- Complot

THE USER MAY SPECIFYING THE DATA TO BE COMPARED BY INPUTTING UP Complot

TO 100 MAT/MT/ENERGY OR ZA/MT/ENERGY RANGES. IF THE UPPER LIMIT Complot

OF THE MAT OR ZA RANGE IS LESS THAN THE LOWER LIMIT IT WILL BE SET Complot

EQUAL TO THE LOWER LIMIT (I.E. THIS INDICATE ONLY COMPARE ONE Complot

MAT OR ZA). IF THE UPPER LIMIT IS STILL ZERO IT WILL BE SET TO Complot

9999 (NO LIMIT). IF THE UPPER MF OR MT LIMIT IS ZERO IT WILL BE Complot

SET TO 99 OR 999, RESPECTIVELY (NO LIMIT). IF THE UPPER ENERGY Complot

LIMIT IS ZERO IT WILL BE SET TO A LARGE NUMBER (NO LIMIT). Complot

Complot

THE LIST OF RANGES MUST BE TERMINATED BY A BLANK LINE (I.E. ZERO Complot

LOWER AND UPPER MAT/MF/MT OR ZA/MF/MT LIMITS). Complot

Complot

IF THE FIRST RANGE LINE IS BLANK THIS LINE WILL TERMINATE THE Complot

LIST OF REQUESTS (I.E. A SECOND BLANK LINE NEED NOT BE INPUT) Complot

AND ALL PHYSICALLY COMPARABLE DATA WILL BE PLOTTED. Complot

Complot

WHICH REACTIONS WILL BE PLOTTED Complot

------------------------------- Complot

THOSE REACTIONS WITH THE SAME (ZA, MF, MT) WILL BE COMPARED, BUT Complot

ONLY THOSE DATA WHICH DIFFER BY A USER SPECIFIED ALLOWABLE Complot

DIFFERENCE WILL BE PLOTTED. IN ORDER TO FORCE ALL COMPARABLE Complot

REACTIONS TO BE PLOTTED THE USER NEED ONLY SPECIFY AN ALLOWABLE Complot

DIFFERENCE OF ZERO. Complot

Complot

EQUIVALENT REACTIONS Complot

-------------------- Complot

IN ORDER TO COMPARE REACTIONS WHICH HAVE DIFFERENT ZA, MF OR MT Complot

THE USER IS ALLOWED TO SPECIFY AN EQUIVALENCE LIST OF UP TO Complot

100 (ZA,MF,MT) COMBINATIONS ON THE MASTER FILE WHICH ARE TO BE Complot

EQUATED TO DIFFERENT (ZA,MF,MT) ON THE SECOND FILE. THIS OPTION Complot

MAY BE USED TO COMPARE SIMILAR REACTIONS FROM DIFFERENT MATERIALS Complot

(E.G. IRON AND NICKEL INELASTIC SCATTERING) OR DIFFERENT REACTIONS Complot

FROM THE SAME OR DIFFERENT MATERIALS (E.G. U-235 CAPTURE AND Complot

FISSION - IN WHICH CASE THE RATIO WILL BE THE CAPTURE TO FISSION Complot

RATIO) OR THE SAME REACTION IN DIFFERENT VERSIONS OF THE ENDF/B Complot

FORMAT WHICH MAY BE ASSIGNED DIFFERENT MT NUMBERS, E.G., THE Complot

PHOTOELECTRIC CROSS SECTION IS MT=602 IN ENDF/B-V AND EARLIER Complot

VERSIONS OF ENDF/B, BUT IS MT=522 IN ENDF/B-VI. Complot

Complot

IN THESE EQUIVALENCE LISTS A ZERO FIELD IMPLIES ALL. FOR EXAMPLE, Complot

TO EQUATE MT=522 FROM ONE FILE TO MT=602 ON THE OTHER, FOR ALL Complot

MATERIALS, ONE NEED ONLY SPECIFY ZA=0, MF=23, MT=522 EQUIVALENT Complot

TO ZA=0, MF=23 AND MT=602. Complot

Complot

PLOT FORMATS Complot

------------ Complot

THE TWO CROSS SECTIONS ARE CONSIDERED TO BE A STANDARD (THE FIRST Complot

CROSS SECTION) AND A CROSS SECTION TO BE COMPARED TO THE STANDARD Complot

(THE SECOND CROSS SECTION). THE OUTPUT FROM THIS PROGRAM IS A Complot

SERIES OF PLOTS. EACH PLOT WILL CONTAIN THE STANDARD CROSS SECTION Complot

AND IN ADDITION THE USER MAY SPECIFY THAT EACH PLOT ALSO CONTAIN Complot

THE SECOND CROSS SECTION AND/OR THE RATIO OF THE SECOND CROSS Complot

SECTION TO THE FIRST CROSS SECTION. Complot

Complot

THE USER MAY SELECT ONE OF THE FOLLOWING FIVE PLOT FORMATS (THE Complot

NUMBER PRECEDING THE OPTION IS THE VALUE OF THE PLOT MODE SELECTOR Complot

THAT THE USER SHOULD SPECIFY AS INPUT ON THE FIRST LINE). Complot

Complot

(0) THE STANDARD CROSS SECTION (I.E. FIRST EVALUATION) AND THE Complot

RATIO OF THE SECOND EVALUATION TO THE FIRST EVALUATION. THE Complot

DATA WILL BE PRESENETED AS TWO SUB-PLOTS PER PLOT WITH THE Complot

STANDARD CROSS SECTION IN THE UPPER HALF OF THE PLOT AND THE Complot

RATIO IN THE LOWER HALF OF THE PLOT. Complot

Complot

(1) THE STANDARD CROSS SECTION (I.E. FIRST EVALUATION) AND THE Complot

SECOND EVALUATION. THE DATA WILL BE PRESENTED AS TWO SUB-PLOTS Complot

PER PLOT WITH THE STANDARD CROSS SECTION ON THE UPPER HALF Complot

OF THE PLOT AND THE SECOND CROSS SECTION IN THE LOWER HALF OF Complot

THE PLOT. Complot

Complot

(2) THE STANDARD CROSS SECTION (I.E. FIRST EVALUATION) AND THE Complot

SECOND EVALUATION. THE DATA WILL BE PRESENTED AS ONE PLOT Complot

CONTAINING BOTH THE STANDARD AND SECOND CROSS SECTION. THE Complot

STANDARD CROSS SECTION WILL BE PRESENTED AS A SOLID LINE AND Complot

THE SECOND CROSS SECTION WILL BE PRESENTED AS A DASHED LINE. Complot

Complot

(3) THE STANDARD CROSS SECTION, SECOND CROSS SECTION AND RATIO OF Complot

THE SECOND CROSS SECTION TO THE FIRST CROSS SECTION. THE DATA Complot

WILL BE PRESENTED AS THREE SUB-PLOTS PER PLOT WITH THE Complot

STANDARD CROSS SECTION IN THE UPPER THIRD OF THE PLOT, THE Complot

SECOND CROSS SECTION IN THE MIDDLE THIRD AND THE RATIO OF THE Complot

TWO IN THE LOWER THIRD OF THE PLOT (RECOMMENDED OPTION). Complot

Complot

(4) THE STANDARD CROSS SECTION, SECOND CROSS SECTION AND RATIO OF Complot

THE SECOND CROSS SECTION TO THE FIRST CROSS SECTION. THE DATA Complot

WILL BE PRESENTED AS TWO SUB-PLOTS PER PLOT WITH THE STANDARD Complot

AND SECOND CROSS SECTION ON THE SAME SUB-PLOT IN THE UPPER Complot

TWO THIRDS OF THE PLOT AND THE RATIO OF THE TWO IN THE LOWER Complot

THIRD OF THE PLOT. THE STANDARD CROSS SECTION WILL BE Complot

PRESENTED AS A SOLID LINE AND THE SECOND CROSS SECTION WILL BE Complot

PRESENTED AS A DASHED LINE. Complot

Complot

ADDITIONAL PLOT FEATURES Complot

------------------------ Complot

IN ADDITION TO THE CROSS SECTIONS AND/OR RATIO THE FOLLOWING Complot

INFORMATIONS WILL BE INCLUDED ON EACH PLOT. Complot

Complot

(1) AN IDENTIFICATION FOR EACH SET OF CROSS SECTIONS (UP TO 30 Complot

CHARACTERS FOR EACH SET). Complot

Complot

(2) THE MAXIMUM NEGATIVE AND POSITIVE PER-CENT DIFFERENCE BETWEEN Complot

THE TWO CROSS SECTIONS. Complot

Complot

(3) ARROWS INDICATING THE ENERGY AT WHICH THE MAXIMUM DIFFERENCES Complot

(MINIMUM AND MAXIMUM RATIO) OCCUR. Complot

Complot

(4) THE ENERGY LIMITS OF THE RESOLVED AND UNRESOLVED RESONANCE Complot

REGION (IF THEY FALL WITHIN THE ENERGY LIMITS OF THE PLOT). Complot

Complot

RATIO DATA Complot

---------- Complot

IF RATIO OUTPUT IS REQUESTED THE RATIO WILL BE DEFINED AT EACH Complot

ENERGY THAT APPEARS IN EITHER EVALUATION. BETWEEN THESE ENERGIES Complot

THE RATIO WILL BE PLOTTED ASSUMING LINEAR DEPENDENCE BETWEEN Complot

TABULATED VALUES. FOR HISTOGRAM OR LINEARLY INTERPOLABLE CROSS Complot

SECTIONS THIS REPRESENTATION WILL POINT OUT ALL EXTREMA OF THE Complot

RATIO, BUT NOT NECESSARILY THE ENERGY DEPENDENCE BETWEEN TABULATED Complot

VALUES. Complot

Complot

IF THE EVALUATED DATA IS NOT IN EITHER HISTOGRAM OR LINRARLY Complot

INTERPOLABLE FORM THE RATIO MAY NOT EVEN FIND ALL EXTREMA. FOR Complot

EXAMPLE, IF ONE EVALUATION IS LINEARLY INTERPOLABLE AND THE Complot

OTHER NON-LINEAR, BUT BOTH AGREE AT ALL TABULATED ENERGIES THE Complot

RATIO WILL APPEAR TO BE EQUAL TO UNITY AT ALL ENERGIES, BUT IN Complot

FACT THE CROSS SECTION BETWEEN TABULATED ENERGIES MAY BE QUITE Complot

DIFFERENT USING LINEAR VS. NON-LINEAR INTERPOLATION. FOR THIS Complot

REASON ONLY LINEARLY INTERPOLABLE OR HISTOGRAM DATA IS ALLOWED Complot

AS INPUT TO THIS PROGRAM. Complot

Complot

LINEAR INTERPOLABLE Complot

------------------- Complot

ALL CROSS SECTIONS MAY BE CONVERTED TO LINEARLY INTERPOLABLE FORM Complot

BE USING PROGRAM LINEAR (UCRL-50400, VOL. 17, PART A). Complot

Complot

HISTOGRAM Complot

--------- Complot

ALL LINEARLY INTERPOLABLE CROSS SECTION MAY BE CONVERTED TO Complot

HISTOGRAM (I.E. MULTIGROUP) FORM BY USING PROGRAM GROUPIE Complot

(UCRL-50400, VOL. 17, PART D). Complot

Complot

INPUT UNITS Complot

----------- Complot

UNIT DESCRIPTION Complot

---- ----------- Complot

2 INPUT LINE Complot

9 MT DEFINITIONS. Complot

10 FIRST ENDF/B FORMATTED EVALUATION (STANDARD). Complot

11 SECOND ENDF/B FORMATTED EVALUATION. Complot

17 SOFTWARE CHARACTERS. Complot

18 SOFTWARE SYMBOLS AND LINE TYPES Complot

Complot

OUTPUT UNITS Complot

------------ Complot

UNIT DESCRIPTION Complot

---- ----------- Complot

3 NORMAL OUTPUT REPORT. Complot

16 PLOTTER UNIT Complot

Complot

SCRATCH UNITS Complot

------------- Complot

UNIT DESCRIPTION Complot

---- ----------- Complot

12 SCRATCH UNIT FOR FIRST EVALUATION Complot

13 SCRATCH UNIT FOR SECOND EVALUATION Complot

14 SCRATCH UNIT FOR RATIO (ONLY USED IF RATIOS REQUESTED). Complot

Complot

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Complot

--------------------------------------------------------------- Complot

UNIT FILE NAME Complot

---- ---------- Complot

2 COMPLOT.INP Complot

3 COMPLOT.LST Complot

9 MT.DAT Complot

10 ENDFB.IN1 (OR AS READ FROM INPUT) Complot

11 ENDFB.IN2 (OR AS READ FROM INPUT) Complot

12-14 (SCRATCH) Complot

15 PLOT.CHR Complot

16 (PLOTTER UNIT...USUALLY A DUMMY) Complot

Complot

INPUT PARAMETERS Complot

------------------------------------------------------------------ Complot

LINE COLUMNS FORMAT DESCRIPTION Complot

---- ------- ------ ----------- Complot

1 1-11 E11.4 LOWER X LIMIT OF PLOTTER Complot

12-22 E11.4 UPPER X LIMIT OF PLOTTER Complot

23-33 E11.4 LOWER Y LIMIT OF PLOTTER Complot

34-44 E11.4 UPPER Y LIMIT OF PLOTTER Complot

45-55 I11 NUMBER OF PLOTS PER FRAME IN X DIRECTION Complot

56-66 I11 NUMBER OF PLOTS PER FRAME IN Y DIRECTION Complot

67-70 F4.1 CHARACTER SIZE MULTIPLIER Complot

= 0 TO 1 - NORMAL CHARACTER SIZE Complot

= OTHERWISE - CHARACTERS SCALED BY THIS Complot

FACTOR Complot

Complot

PLOT ORIENTATION IS BASED ON THE UPPER X Complot

LIMIT Complot

= .GT.0 - X HORIZONTAL/Y VERTICAL Complot

= .LT.0 - Y HORIZONTAL/X VERTICAL Complot

AFTER TESTING THE UPPER X LIMIT WILL BE Complot

SET TO ITS ABSOLUTE VALUE. Complot

2 1-72 A60 FILENAME FOR FIRST ENDF/B DATA FILE Complot

(LEAVE BLANK FOR ENDFB.IN1) Complot

3 1-72 A60 FILENAME FOR SECOND ENDF/B DATA FILE Complot

(LEAVE BLANK FOR ENDFB.IN2) Complot

4 1-11 I11 RETRIEVAL MODE (0=MAT, 1=ZA) Complot

12-22 I11 GRID (SPEED) OPTION. Complot

= 0 - TICK MARKS ON BORDER Complot

= 1 - SOLID AT COARSE INTERVALS Complot

= 2 - DASHED AT COARSE INTERVALS Complot

= 3 - SOLID AT COARSE AND FINE INTERVALS Complot

= 4 - DASHED AT COARSE AND FINE INTERVALS Complot

= 5 - SOLID COARSE/DASHED FINE INTERVALS Complot

23-33 I11 SHOULD BORDER BE PLOTTED AROUND EACH PLOT Complot

= 0 - NO Complot

= 1 - YES Complot

34-44 I11 LINE THICKNESS Complot

= 0 TO 5 - LINES AND CHARACTERS Complot

=-1 TO -5 - ONLY LINES Complot

45-55 I11 OUTPUT MODE Complot

=-1 - ONLY COMPARISON LISTING. NO PLOTS. Complot

= 0 - CROSS SECTION OVER RATIO. Complot

= 1 - CROSS SECTION OVER CROSS SECTION. Complot

= 2 - TWO CROSS SECTIONS ON SAME PLOT. Complot

= 3 - CROSS SECTION OVER CROSS SECTION OVER Complot

RATIO. Complot

= 4 - TWO CROSS SECTIONS ON SAME PLOT OVER Complot

RATIO. Complot

56-66 I11 STARTING PLOT NUMBER Complot

= 0 - DO NOT NUMBER PLOTS Complot

= .GT.0 - NUMBER PLOTS IN LOWER LEFT HAND Complot

CORNER STARTING WITH INPUT NUMBER Complot

67-70 I41 BACKGROUND COLOR Complot

= 0 = BLACK Complot

= OTHERWISE = WHITE Complot

5 1-11 E11.4 ALLOWABLE FRACTIONAL DIFFERENCE. USED WHEN Complot

PLOTTING RATIOS. ANY REACTION WHERE THE Complot

TWO EVALUATIONS DIFFER BY MORE THAN THE Complot

ALLOWABLE DIFFERENCE WILL BE PLOTTED. IF Complot

ZERO IS INPUT THE STANDARD ALLOWABLE Complot

DIFFERENCE OF 0.001 (0.1 PER-CENT) WILL BE Complot

USED. Complot

12-22 E11.4 MAXIMUM ALLOWABLE RATIO. IF RATIOS ARE Complot

PLOTTED THEY WILL BE IN THE RANGE RATMAX Complot

TO 1/RATMAX. IF 0.0 IS INPUT THERE WILL Complot

BE NO LIMIT ON THE RANGE OF THE RATIOS. Complot

THIS OPTION MAY BE USED TO IGNORE LARGE Complot

DIFFERENCES OVER VERY NARROW ENERGY RANGES Complot

(WHICH MAY BE UNIMPORTANT) AND ALLOW ONE Complot

TO SEE IMPORTANT, BUT SMALLER DIFFERENCES, Complot

OVER EXTENDED ENERGY RANGES. Complot

6 1-40 40A1 IDENTIFICATION FOR UPPER EVALUATIONS Complot

7 1-40 40A1 IDENTIFICATION FOR LOWER EVALUATIONS Complot

(IDENTIFICATIONS SHOULD BE LEFT ADJUSTED Complot

TO START IN COLUMN 1). Complot

8-N 1- 6 I6 LOWER MAT OR ZA LIMIT (SEE SELECTION MODE, Complot

INPUT LINE 1, COLUMNS 1-11). Complot

7- 8 I2 LOWER MF LIMIT Complot

9-11 I3 LOWER MT LIMIT Complot

12-22 E11.4 LOWER ENERGY LIMIT Complot

23-28 I6 UPPER MAT OR ZA LIMIT (SEE SELECTION MODE, Complot

INPUT LINE 1, COLUMNS 1-11). Complot

29-30 I2 UPPER MF LIMIT Complot

31-33 I3 UPPER MT LIMIT Complot

34-44 E11.4 UPPER ENERGY LIMIT Complot

45-55 I11 IDENTIFY EVALUATED DATA POINTS OPTION. Complot

= 0 - DO NOT IDENTIFY DATA POINTS. Complot

= 1 - IDENTIFY DATA POINTS (BY DRAWING A Complot

SMALL BOX AROUND EACH POINT). Complot

56-66 I11 INTERACTIVE INPUT FLAG Complot

= 0 - NO INTERACTIVE INPUT ALLOWED Complot

= 1 - INTERACTIVE INPUT ALLOWED Complot

*SETTING THIS OPTION =1 WILL TURN ON THE Complot

MOUSE AFTER EACH PLOT AND ALLOW YOU TO Complot

INTERACTIVELY SPECIFY PLOT LIMITS. Complot

*IF YOU DO NOT WISH TO INTERACT WITH A PLOT Complot

OR IF YOU HAVE NO INTERACTIVE CAPABILITY Complot

THIS OPTION SHOULD BE SET = 0. Complot

Complot

*WARNING...DATA POINTS IDENTIFIED OPTION IS Complot

NOT RECOMMENDED FOR PLOTS CONTAINING MANY Complot

(I.E. THOUSANDS) OF DATA POINTS SINCE IT Complot

WILL MERELY INCREASE THE RUNNING TIME OF Complot

THE PROGRAM AND STILL NOT ALLOW ONE TO Complot

ACCURATELY SEE DATA POINTS. Complot

Complot

*UP TO 100 MAT OR ZA RANGES ARE ALLOWED. Complot

THE LIST IS TERMINATED BY A BLANK LINE. Complot

IF THE UPPER LIMIT IS LESS THAN THE LOWER Complot

LIMIT IT WILL BE SET EQUAL TO THE LOWER Complot

LIMIT. IF THE FIRST RANGE LINE IS BLANK Complot

ALL DATA WILL BE RETRIEVED. IF THE UPPER Complot

MT LIMIT IS ZERO IT WILL BE SET EQUAL TO Complot

999 (NO LIMIT). IF THE UPPER ENERGY LIMIT Complot

IS ZERO IT WILL BE INTREPRETED TO MEAN NO Complot

LIMIT. IF THE FIRST RANGE LINE SPECIFIES Complot

ZERO LOWER AND UPPER MAT OR ZA RANGE IT Complot

WILL TERMINATE THE LIST BE RANGE LINES Complot

(A SECOND BLANK LINE NEED NOT BE INPUT) Complot

AND THE ENTIRE RANGE OF MATS WILL BE Complot

COMPARED FOR THE SPECIFIED MT AND ENERGY Complot

RANGES. Complot

Complot

N+1-M EQUIVALENCES Complot

1- 6 I6 MASTER ZA. Complot

7- 8 I2 MASTER MF. Complot

9-11 I3 MASTER MT. Complot

12-17 I6 EQUIVALENT ZA FROM SECOND FILE. Complot

18-19 I2 EQUIVALENT MF FROM SECOND FILE. Complot

20-22 I3 EQUIVALENT MT FROM SECOND FILE. Complot

23-33 E11.4 MULTIPLICATION FACTOR. ANY EQUATED ZA,MF, Complot

MT DATA WILL BE MULTIPLIED BY THIS FACTOR. Complot

*THIS OPTION MAY BE USED TO RE-NORMALIZE Complot

THE SECOND CROSS SECTION OR IF COMPARING Complot

ONE CONSTITUENT OF A MIXTURE TO THE MIXED Complot

CROSS SECTION THIS MAY BE USED TO CONVERT Complot

THE SECOND CROSS SECTION TO BARNS PER MIXED Complot

ATOM BY USING A MULTIPLICATION FACTOR WHICH Complot

IS EQUAL TO THE NUMBER OF ATOMS OF THE ONE Complot

CONSTITUENT PER ATOM OF THE MIXTURE. Complot

= 0.0 - ON INPUT WILL BE INTERPRETED AS 1.0 Complot

(WITH THIS CONVENTION THE USER NEED ONLY Complot

INPUT MULTIPLICATION FACTORS IF THEY ARE Complot

NOT 1.0). Complot

*UP TO 100 MAT OR ZA EQUIVALENCES ARE Complot

ALLOWED. Complot

*THE LIST IS TERMINATED BY A BLANK LINE. Complot

*A ZERO INPUT FIELD IMPLIES ALL. TO EQUATE Complot

A GIVEN MT NUMBER TO ANOTHER MT NUMBER YOU Complot

NEED MERELY SPECIFY ZA=0 ON INPUT. Complot

*NOTE, IN ALL CASES THE TITLE AT TOP OF PLOT Complot

WILL ONLY INDENTIFY MASTER (ZA,MF,MT). THE Complot

USER INPUT TITLES MUST BE USED TO IDENTIFY Complot

THE SECOND REACTION (SEE, EXAMPLE INPUT 4 Complot

BELOW). Complot

Complot

Complot

EXAMPLE DEFINITION OF PLOTTER Complot

----------------------------- Complot

THE FIRST INPUT LINE DEFINES THE DIMENSIONS OF THE PLOTTER BEING Complot

USED IN ANY UNITS (INCHES, CENTIMETERS, MILLIMETERS, ANYTHING) Complot

WHICH APPLY TO THE PLOTTER. IN ADDITION THE FIRST LINE DEFINES Complot

HOW MANY PLOTS SHOULD APPEAR ON EACH FRAME. THE PLOTTING AREA Complot

DEFINED ON THE FIRST INPUT LINE MAY BE SUBDIVIDED INTO ANY NUMBER Complot

OF PLOTS IN THE X AND Y DIRECTION. FOR EXAMPLE, TO PRODUCE A Complot

SERIES OF FRAMES EACH CONTAINING 3 PLOTS IN THE X DIRECTION AND Complot

2 PLOTS IN THE Y DIRECTION (6 PLOTS PER FRAME) COLUMN 45-55 OF Complot

THE FIRST INPUT LINE SHOULD BE 3 AND COLUMNS 56-66 SHOULD BE 2. Complot

Complot

IF THE LOCAL PLOTTER USES DIMENSIONS OF INCHES IN ORDER TO OBTAIN Complot

10 X 10 INCH FRAMES WITH 3 X 2 PLOTS PER FRAME THE FIRST INPUT Complot

LINE SHOULD BE, Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

Complot

IF THE LOCAL PLOTTER USES DIMENSION OF MILLIMETERS THE SAME Complot

PHYSICAL SIZE PLOT MAY BE OBTAINED IF THE FIRST INPUT LINE IS, Complot

Complot

0.0 254.0 0.0 254.0 3 2 Complot

Complot

FOR SIMPLICITY THE FOLLOWING EXAMPLE INPUTS WILL NOT DISCUSS THE Complot

PHYSICAL DIMENSIONS OF THE PLOTTER AND THE FIRST INPUT LINE WILL Complot

IN ALL CASES INDICATE 10 X 10 INCH PLOTS WITH ONLY 1 PLOT PER Complot

FRAME. Complot

Complot

IN THE FOLLOWING EXAMPLES IN ALL CASES THESE OPTIONS WILL BE USED, Complot

1) DASHED GRID - COLUMNS 12-22 OF SECOND INPUT LINE = 1 Complot

2) NO BORDER - COLUMNS 23-33 OF SECOND INPUT LINE = 0 Complot

3) LINE THICKNESS - COLUMNS 34-44 OF SECOND INPUT LINE = -2 Complot

4) OUTPUT MODE - COLUMNS 45-55 OF SECOND INPUT LINE = 3 Complot

5) FIRST PLOT NUMBER - COLUMNS 56-66 OF SECOND INPUT LINE = 1 Complot

Complot

EXAMPLE INPUT 1 Complot

--------------- Complot

RETRIEVE MATS 1023, 1056 AND 1065 THROUGH 1072, MT = 1 AND 2 Complot

(TOTAL AND ELASTIC) FROM THE FIRST INPUT FILE AND COMPARE TO Complot

ANY SECTION FROM THE SECOND FILE THAT HAS THE SAME ZA/MF/MT. ONLY Complot

COMPARE DATA OVER THE ENERGY RANGE 0.1 EV TO 1 KEV. IDENTIFY Complot

THE TWO SETS OF DATA AS ENDF/B-V AND ENDF/B-IV, RESPECTIVELY. Complot

ONLY PLOT THOSE REACTIONS WHICH DIFFER AT ONE OR MORE ENERGIES Complot

BY MORE THAN 1 PER-CENT (NOTE, 1 PER-CENT = 0.01 AS INPUT Complot

FRACTION). NO EQUIVALENT REACTIONS ARE SPECIFIED. FILERNAMES Complot

ARE STANDARD (THSE CAN EITHER BE EXPLICITLY INCLUDED, OR SIMPLY Complot

LEFT BLANK). Complot

Complot

THE FOLLOWING 12 INPUT LINES ARE REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

ENDFB.IN1 Complot

ENDFB.IN2 Complot

0 1 0 -2 3 1 Complot

0.01 0.0 Complot

ENDF/B-V DATA (STANDARD) Complot

ENDF/B-IV DATA Complot

1023 3 1 0.1 3 2 1000.0 0 Complot

1056 3 1 0.1 3 2 1000.0 0 Complot

1065 3 1 0.1 1072 3 2 1000.0 0 Complot

(TERMINATES REQUEST LIST) Complot

(TERMINATES EQUIVALENCE LIST) Complot

Complot

EXAMPLE INPUT 2 Complot

--------------- Complot

TO USE ALL OF THE SAME OPTIONS AS SPECIFIED IN EXAMPLE INPUT 1, Complot

EXCEPT TO RETRIEVE U-235, U-238 AND PU-239 THROUGH PU-242 THE Complot

FOLLOWING 12 INPUT LINES ARE REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

ENDFB.IN1 Complot

ENDFB.IN2 Complot

1 1 0 -2 3 1 Complot

0.01 0.0 Complot

ENDF/B-V DATA (STANDARD) Complot

ENDF/B-IV DATA Complot

92235 3 1 0.1 3 2 1000.0 0 Complot

92238 3 1 0.1 3 2 1000.0 0 Complot

94239 3 1 0.1 94242 3 2 1000.0 0 Complot

(TERMINATES REQUEST LIST) Complot

(TERMINATES EQUIVALENCE LIST) Complot

EXAMPLE INPUT 3 Complot

--------------- Complot

TO USE ALL OF THE SAME OPTIONS AS SPECIFIED IN EXAMPLE INPUT 1, Complot

EXCEPT TO RETRIEVE AND COMPARE ALL MATS THE FOLLOWING 10 INPUT Complot

LINES ARE REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

ENDFB.IN1 Complot

ENDFB.IN2 Complot

0 1 0 -2 3 1 Complot

0.01 0.0 Complot

ENDF/B-V DATA (STANDARD) Complot

ENDF/B-IV DATA Complot

1 1 1 0.0 999999999 0.0 0 Complot

(TERMINATES REQUEST LIST) Complot

(TERMINATES EQUIVALENCE LIST) Complot

NOTE, ZERO LOWER AND UPPER Complot

MAT LIMITS INDICATES NO LIMIT. Complot

Complot

EXAMPLE INPUT 4 Complot

--------------- Complot

RETRIEVE U-235 AND EQUATE THE FISSION CROSS SECTION (MT=18) ON Complot

THE MASTER FILE TO CAPTURE (MT=102) ON THE SECOND FILE. PLOT Complot

THE CAPTURE, FISSION AND CAPTURE TO FISSION RATIO OVER THE ENERGY Complot

RANGE 0.0253 EV TO 1 KEV. THE FOLLOWING 11 INPUT LINES ARE Complot

REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

ENDFB.IN1 Complot

ENDFB.IN2 Complot

1 1 0 -2 3 1 Complot

0.01 0.0 Complot

FISSION Complot

CAPTURE Complot

92235 3 18 0.0253 92235 3 18 1000.0 0 Complot

(TERMINATES REQUEST LIST) Complot

92235 3 18 92235 3102 (MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST) Complot

Complot

EXAMPLE INPUT 5 Complot

--------------- Complot

IN DIFFERENT VERSIONS OF THE ENDF/B FORMAT DIFFERENT MT NUMBERS Complot

ARE ASSIGNED TO THE SAME REACTION. FOR EXAMPLE, IN ENDF/B-V AND Complot

EARLIER VERSIONS OF ENDF/B THE PHOTOELECTRIC CROSS SECTION IS Complot

MT=602, WHILE IN ENDF/B-VI IT IS MT=522. IN ORDER TO COMPARE Complot

ASSUMING THAT THE MASTER IS ENDF/B-VI AND THE OTHER ENDF/B FILE Complot

IS ENDF/B-V (OR EARLIER) YOU MAY EQUATE MT=522 TO 602. Complot

Complot

WHEN COMPARING PHOTOELECTRIC CROSS SECTIONS WE EXPECT THERE TO BE Complot

LARGE DIFFERENCES NEAR EDGES, SINCE IT IS UNLIKELY THAT TWO Complot

INDEPENDENT EVALUATIONS USE EXACTLY THE SAME EDGE ENERGIES. FROM Complot

A PRACTICAL VIEWPOINT THESE DIFFERENCES ARE NOT IMPORTANT IF THEY Complot

ONLY OCCUR OVER NARROW ENERGY RANGES NEAR ENERGIES. HOWEVER THESE Complot

LARGE DIFFERENCES MAY MAKE IT DIFFICULT TO SEE DIFFERENCES OVER Complot

OTHER ENERGY RANGES, WHICH MAY BE IMPORTANT. IN ORDER TO BE ABLE Complot

TO SEE IMPORTANT DIFFERENCES IN THE FOLLOWING COMPARISON WE WILL Complot

CONSTRAIN THE PLOTTED RATIO TO THE RANGE ABOUT 0.9 TO 1.1 IN Complot

ORDER TO BE ABLE TO SEE DIFFERENCES OF UP TO 10 PER-CENT. WE WILL Complot

DO THIS BY SPECIFYING A MAXIMUM RATIO OF 1.1, WHICH WILL IN TURN Complot

DEFINE A MINIMUM RATIO OF 1/1.1, OR ABOUT 0.9. Complot

Complot

IN ORDER TO COMPARE THE PHOTOELECTRIC CROSS SECTION FOR ALL Complot

MATERIALS THE FOLLOWING 11 INPUT LINES ARE REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

ENDFB.IN1 Complot

ENDFB.IN2 Complot

0 1 0 -2 3 1 Complot

0.01 1.1 Complot

ENDF/B-VI Complot

ENDF/B-V Complot

023522 999923522 0 Complot

(TERMINATES REQUEST LIST) Complot

023522 023602 (MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST) Complot

Complot

EXAMPLE INPUT 6 Complot

--------------- Complot

THE SAME EXAMPLE AS ABOVE, EXCEPT THAT DIFFERENT FILENAMES WILL Complot

BE USED TO READ THE DATA FROM A FILE TREE STRUCTURE. THE FOLLOWING Complot

11 INPUT LINES ARE REQUIRED. Complot

Complot

0.0 10.0 0.0 10.0 3 2 Complot

/Evaluated/ENDFB6/PHOTON.IN Complot

/Evaluated/ENDFB5/PHOTON.IN Complot

0 1 0 -2 3 1 Complot

0.01 1.1 Complot

ENDF/B-VI Complot

ENDF/B-V Complot

023522 999923522 0 Complot

(TERMINATES REQUEST LIST) Complot

023522 023602 (MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST) Complot

Complot

EXAMPLE INPUT 7 Complot

--------------- Complot

THE OUTPUT FOR ALL OF THE ABOVE EXAMPLES ARE ORIENTED WITH X Complot

HORIZONTAL AND Y VERTICAL. TO CHANGE THE ORIENTATION OF THE PLOTS Complot

YOU NEED MERELY SPECIFY A NEGATIVE UPPER X LIMIT OF THE SIZE OF Complot

THE PLOTS ON THE FIRST INPUT LINE. Complot

Complot

THE FOLLOWING EXAMPLE IS EXACTLY THE SAME AS THE ABOVE EXAMPLE, Complot

EXCEPT THAT THE ORIENTATION OF THE PLOTS HAS BEEN CHANGED. THE Complot

FOLLOWING 11 INPUT LINES ARE REQUIRED. Complot

Complot

0.0 -10.0 0.0 10.0 3 2 Complot

/Evaluated/ENDFB6/PHOTON.IN Complot

/Evaluated/ENDFB5/PHOTON.IN Complot

0 1 0 -2 3 1 Complot

0.01 1.1 Complot

ENDF/B-VI Complot

ENDF/B-V Complot

023522 999923522 0 Complot

(TERMINATES REQUEST LIST) Complot

023522 023602 (MULTIPLICATION OF 1.0 INFERRED) Complot

(TERMINATES EQUIVALENCE LIST) Complot

Complot

===== PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Complot

Complot

NON-INTERACTIVE Complot

------------------------------------------------------------------ Complot

THIS PROGRAM USES A SIMPLE CALCOMP LIKE INTERFACE INVOLVING Complot

ONLY 5 SUBROUTINES, Complot

Complot

STARPLOT - INITIALIZE PLOTTER Complot

NEXTPLOT - CLEAR SCREEN FOR NEXT PLOT Complot

ENDPLOTS - TERMINATE PLOTTING Complot

Complot

PLOT(X,Y,IPEN) - DRAW OR MOVE FROM LAST LOCATION TO (X,Y), Complot

END OF CURRENT PLOT OR END OF PLOTTING. Complot

IPEN = 2 - DRAW Complot

= 3 - MOVE Complot

Complot

PEN(IPEN) - SELECT COLOR. Complot

IPEN- COLOR = 1 TO N (N = ANY POSITIVE INTEGER) Complot

Complot

BOXCOLOR(X,Y,IFILL,IBORDER) - FILL A RECTANGLE WITH COLOR Complot

X,Y = DEFINE THE CORNERS OF THE BOX Complot

IFILL = COLOR TO FILL BOX WITH Complot

IBORDER = COLOR OF BORDER OF BOX Complot

Complot

INTERACTIVE Complot

------------------------------------------------------------------ Complot

THIS PROGRAM INCLUDES AN INTERACTIVE INTERFACE FOR USE WITH A Complot

MOUSE. THE INTERFACE INVOLVES 2 SUBROUTINE, Complot

Complot

INTERACT(MYACTION) - WHETHER OR NOT INTERACTION Complot

MYACTION = 0 - NO (RETURNED BY INTERACT) Complot

= 1 - YES (RETURNED BY INTERACT) Complot

Complot

MOUSEY(IWAY,XI,YI,IWAY1,IWAY2) - READ POSITION OF MOUSE Complot

IWAY = 0 - NO INPUT Complot

= 1 - LEFT BUTTON Complot

= 2 - MIDDLE BUTTON Complot

= 3 - RIGHT BUTTON Complot

= 4 - KEYBOARD INPUT Complot

XI = X POSITION IN LOCAL UNITS Complot

YI = Y POSITION IN LOCAL UNITS Complot

IWAY1 = MINIMUM ALLOWABLE IWAY Complot

IWAY2 = MAXIMUM ALLOWABLE IWAY Complot

Complot

AS USED BY THIS PROGRAM IWAY1 = 1 Complot

IWAY2 = 4 Complot

KEYBOARD INPUT (IWAY=4) MEANS NO ZOOMED PLOT REQUESTED. Complot

MOUSE INPUT (IWAY=1 TO 3) MEANS A ZOOMED PLOT IS REQUESTED. Complot

MOUSEY WILL BE CALLED ONCE TO SEE IF A ZOOMED PLOT IS REQUESTED. Complot

IF IT IS XI WILL BE USED TO DEFINE ONE X (E.G., ENERGY) LIMIT OF Complot

THE ZOOMED PLOT. MOUSEY WILL THEN BE CALLED A SECOND TIME TO Complot

DEFINE A SECOND XI TO DEFINE THE OTHER X LIMIT OF THE ZOOMED Complot

PLOT. Complot

Complot

IF YOU DO NOT WANT INTERACTION YOU SHOULD INCLUDE THE FOLLOWING Complot

SUBROUTINES IN YOUR GRAPHIC INTERFACE, Complot

Complot

SUBROUTINE INTERACT(MYACTION) Complot

MYACTION=0 Complot

RETURN Complot

END Complot

SUBROUTINE MOUSEY(IWAY,XI,YI,IWAY1,IWAY2) Complot

IWAY=4 Complot

XI=0.0 Complot

YI=0.0 Complot

RETURN Complot

END Complot

Complot

ALTERNATIVE INTERACTIVE Complot

------------------------------------------------------------------ Complot

IF YOU DO NOT HAVE A MOUSE BUT WOULD STILL LIKE TO INTERACTIVE Complot

INPUT YOU CAN REPLACE SUBROUTINE ACTION IN THIS PROGRAM. Complot

Complot

AS DISTRIBUTED SUBROUTINE ACTION USES A MOUSE TO DEFINE LOWER Complot

AND UPPER ENERGY (OR X) LIMITS WHICH ARE USED TO PRODUCE THE Complot

NEXT PLOT. A CALL TO ACTION IS OF THE FORM, Complot

Complot

CALL ACTION(KACTV,XACT1,XACT2) Complot

Complot

KACTV = 0 - NO INTERACTIVE INPUT Complot

= 1 - INTERACTIVE INPUT Complot

XACT1 = LOWER ENERGY LIMIT Complot

XACT2 = UPPER ENERGY LIMIT Complot

Complot

IF THERE IS NO INTERACTIVE INPUT THE PROGRAM WILL PROCEED TO THE Complot

NEXT PLOT REQUESTED BY NON-INTERACTIVE INPUT. Complot

Complot

IF THERE IS INTERACTIVE INPUT THE PROGRAM WILL USE XACT1 AND Complot

XACT2 TO DEFINE THE ENERGY LIMITS OF THE NEXT PLOT USING THE Complot

SAME DATA AS APPEARED ON THE LAST PLOT. AS WITH NON-INTERACTIVE Complot

INPUT, IF YOU SELECT AN ENERGY RANGE WHERE THE MAXIMUM DIFFERENCE Complot

IS LESS THAN THAT SPECIFIED BY INPUT NO PLOT WILL BE PRODUCED Complot

AND THE CODE WILL PROCEED TO THE NEXT PLOT REQUESTED BY Complot

NON-INTERACTIVE INPUT. Complot

Complot

YOU CAN REPLACE SUBROUTINE ACTION FOLLOWING THE ABOVE CONVENTIONS Complot

TO ALLOW INTERACTION VIA DIRECT READ OF X LIMITS, LIGHTPEN OR Complot

WHATEVER FACILITIES YOU HAVE AVAILABLE. Complot

Complot

INTERFACING Complot

------------------------------------------------------------------ Complot

IN ORDER TO INTERFACE THIS PROGRAM FOR USE ON ANY PLOTTER WHICH Complot

DOES NOT USE THE ABOVE CONVENTIONS IT IS MERELY NECESSARY FOR THE Complot

THE USER TO WRITE 5 SUBROUTINES DESCRIBED ABOVE AND TO THEN CALL Complot

THE LOCAL EQUIVALENT ROUTINES. Complot

Complot

COLOR PLOTS Complot

------------------------------------------------------------------ Complot

TO SELECT PLOTTING COLORS SUBROUTINE PEN (DESCRIBED ABOVE) IS USED Complot

TO SELECT ONE OF THE AVAILABLE COLORS. WHEN RUNNING ON A MAINFRAME Complot

USING AN IBM GRAPHICS TERMINAL OR ON AN IBM-PC USING A HEWLETT- Complot

PACKARD PLOTTER THE GRAPHICS INTERFACE (DESCRIBED ABOVE) WILL Complot

PRODUCE COLOR PLOTS. Complot

Complot

BLACK AND WHITE PLOTS Complot

------------------------------------------------------------------ Complot

WHEN PRODUCING BLACK AND WHITE HARDCOPY ON A MAINFRAME THE USER Complot

SHOULD ADD A DUMMY SUBROUTINE PEN TO THE END OF THE PROGRAM TO Complot

IGNORE ATTEMPTS TO CHANGE COLOR. ADD THE FOLLOWING SUBROUTINE, Complot

Complot

SUBROUTINE PEN(IPEN) Complot

RETURN Complot

END Complot

Complot

CHARACTER SET Complot

------------------------------------------------------------------ Complot

THIS PROGRAM USES COMPUTER AND PLOTTER DEVICE INDEPENDENT SOFTWARE Complot

CHARACTERS. THIS PROGRAM COMES WITH A FILE THAT DEFINES THE PEN Complot

STROKES REQUIRED TO DRAW ALL CHARACTERS ON AN IBM KEYBOARD (UPPER Complot

AND LOWER CASE CHARACTERS, NUMBERS, ETC.) PLUS AN ALTERNATE SET OF Complot

ALL UPPER AND LOWER CASE GREEK CHARACTERS AND ADDITIONAL SPECIAL Complot

SYMBOLS. Complot

Complot

THE SOFTWARE CHARACTER TABLE CONTAINS X AND Y AND PEN POSITIONS TO Complot

DRAW EACH CHARACTER. IF YOU WISH TO DRAW ANY ADDITIONAL CHARACTERS Complot

OR TO MODIFY THE FONT OF THE EXISTING CHARACTERS YOU NEED ONLY Complot

MODIFY THIS TABLE. Complot

Complot

CONTROL CHARACTERS Complot

------------------------------------------------------------------ Complot

IN THE SOFTWARE CHARACTER TABLE ALL CHARACTERS TO BE PLOTTED WILL Complot

HAVE PEN POSITION = 2 (DRAW) OR = 3 (MOVE). IN ADDITION THE TABLE Complot

CURRENTLY CONTAINS 4 CONTROL CHARACTERS, Complot

Complot

PEN POSITION = 0 Complot

---------------- Complot

SHIFT THE NEXT PRINTED CHARACTER BY X AND Y. 3 CONTROL CHARACTERS Complot

ARE PRESENTLY INCLUDED IN THE SOFTWARE CHARACTER TABLE TO ALLOW Complot

SHIFTING. Complot

Complot

{ = SHIFT UP (FOR SUPERSCRIPTS..............X= 0.0, Y= 0.5) Complot

} = SHIFT DOWN (FOR SUBSCRIPTS..............X= 0.0, Y=-0.5) Complot

\ = SHIFT LEFT 1 CHARACTER (FOR BACKSPACE...X=-1.0, Y= 0.0) Complot

Complot

PEN POSITION =-1 Complot

---------------- Complot

SELECT THE NEXT PRINTED CHARACTER FROM THE ALTERNATE CHARACTER Complot

SET. AT PRESENT THIS CONTROL CHARACTER IS, Complot

Complot

] = SWITCH TO ALTERNATE CHARACTER SET Complot

Complot

THESE 4 CONTROL CHARACTERS ARE ONLY DEFINED BY THE VALUE OF THE Complot

PEN POSITION IN THE SOFTWARE CHARACTER TABLE (I.E., THEY ARE NOT Complot

HARD WIRED INTO THIS PROGRAM). AS SUCH BY MODIFYING THE SOFTWARE Complot

CHARACTER TABLE THE USER HAS THE OPTION OF DEFINING ANY CONTROL Complot

CHARACTERS TO MEET SPECIFIC NEEDS. Complot

Complot

THESE CHARACTERS MAY BE USED IN CHARACTER STRINGS TO PRODUCE Complot

SPECIAL EFFECTS. FOR EXAMPLE, TO PLOT SUBSCRIPT 5, B, SUPERSCRIPT Complot

10 USE THE STRING, Complot

Complot

}5B{1{0 Complot

Complot

TO PLOT B, SUBSCRIPT 5 AND SUPERSCRIPT 10 WITH THE 5 DIRECTLY Complot

BELOW THE 1 OF THE 10 WE CAN USE THE BACKSPACE CHARACTER TO Complot

POSITION THE 1 DIRECTLY ABOVE THE 5 USING THE STRING, Complot

Complot

B}5\{1{0 Complot

Complot

TO PLOT UPPER CASE GREEK GAMMA FOLLOWED BY THE WORD TOTAL (I.E., Complot

RESONANCE TOTAL WIDTH) USE THE STRING. Complot

Complot

]G TOTAL Complot

Complot

NOTE, WHEN THESE CONTROL CHARACTERS ARE USED THEY ONLY EFFECT THE Complot

NEXT 1 PRINTED CHARACTER (SEE, ABOVE EXAMPLE OF PLOTTING SUPER- Complot

SCRIPT 10 WHERE THE SHIFT UP CONTROL CHARACTER WAS USED BEFORE THE Complot

1 AND THEN AGAIN BEFORE THE 0 AND THE BACKSPACE AND SHIFT UP Complot

CONTROL CHARACTERS WERE USED IN COMBINATION). Complot

Complot

IF THESE 4 CONTROL CHARACTERS ARE NOT AVAILABLE ON YOUR COMPUTER Complot

YOU CAN MODIFY THE SOFTWARE CHARACTER TABLE TO USE ANY OTHER 4 Complot

CHARACTERS THAT YOU DO NOT NORMALLY USE IN CHARACTER STRINGS (FOR Complot

DETAILS SEE THE SOFTWARE CHARACTER TABLE). Complot

Complot

STANDARD/ALTERNATE CHARACTER SETS Complot

------------------------------------------------------------------ Complot

THE SOFTWARE CHARACTER TABLE CONTAINS 2 SETS OF CHARACTERS WHICH Complot

ARE A STANDARD SET (ALL CHARACTERS ON AN IBM KEYBOARD) AND AN Complot

ALTERNATE SET (UPPER AND LOWER CASE GREEK CHARACTERS AND SPECIAL Complot

CHARACTERS). TO DRAW A CHARACTER FROM THE ALTERNATE CHARACTER SET Complot

PUT A RIGHT BRACKET CHARACTER (]) BEFORE A CHARACTER (SEE THE Complot

ABOVE EXAMPLE AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS Complot

CONTROL CHARACTER WILL ONLY EFFECT THE NEXT 1 PLOTTED CHARACTER. Complot

Complot

SUB AND SUPER SCRIPTS Complot

------------------------------------------------------------------ Complot

TO DRAW SUBSCRIPT PRECEED A CHARACTER BY }. TO DRAW SUPERSCRIPT Complot

PRECEED A CHARACTER BY { (SEE THE ABOVE EXAMPLE AND THE SOFTWARE Complot

CHARACTER TABLE FOR DETAILS). THESE CONTROL CHARACTER WILL ONLY Complot

EFFECT THE NEXT 1 PLOTTED CHARACTER. Complot

Complot

BACKSPACING Complot

------------------------------------------------------------------ Complot

TO BACKSPACE ONE CHARACTER PRECEED A CHARACTER BY \ (SEE, THE Complot

ABOVE EXAMPLE AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS Complot

CONTROL CHARACTER WILL PERFORM A TRUE BACKSPACE AND WILL EFFECT Complot

ALL FOLLOWING CHARACTERS IN THE SAME CHARACTER STRING. Complot

Complot

PLOT DIMENSIONS Complot

--------------- Complot

ARE DEFINED BY USER INPUT. INTERNALLY THE PROGRAM WILL CREATE A Complot

PLOT IN APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. DURING Complot

OUTPUT THE PLOT IS TRANSFORMED TO THE UNITS (INCHES, CENTIMETERS, Complot

MILLIMETERS, WHATEVER) OF THE PLOTTER BEING USED AND OUTPUT. Complot

Complot

===== PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Complot

======================================================================= Complot

======================================================================= Convert

Convert

PROGRAM CONVERT Convert

VERSION 75-1 (APRIL 1975) Convert

VERSION 78-1 (JANUARY 1978) Convert

VERSION 80-1 (AUGUST 1980) IBM VERSION Convert

VERSION 80-2 (DECEMBER 1980) Convert

VERSION 82-1 (JANUARY 1982) Convert

VERSION 83-1 (JANUARY 1983) Convert

VERSION 86-1 (JANUARY 1986)*NEW PROGRAM Convert

*FORTRAN-77/H VERSION Convert

*MULTIPLE INPUT OPTIONS Convert

VERSION 88-1 (AUGUST 1988) *OPTION...INTERNALLY DEFINE ALL I/O Convert

FILE NAMES (SEE, SUBROUTINE FILEIO Convert

FOR DETAILS). Convert

*IMPROVED BASED ON USER COMMENTS. Convert

*ADDED NAMES OPTION TO TURN ON/OFF Convert

STANDARD FILE NAMES. Convert

*ADDED REWIND OPTION TO TURN ON/OFF Convert

REWIND AT START OF PROGRAMS. Convert

*DELETED HARWELL AND JAERI OPTIONS Convert

(PREVIOUSLY ONLY REQUIRED FOR GRAPHIC Convert

INTERFACE. NO LONGER REQUIRED). Convert

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Convert

INSURE PROGRAM WILL NOT DO ANYTHING Convert

CRAZY. Convert

*IMPROVED BASED ON USER COMMENTS. Convert

*ADDED LIVERMORE CIVIC COMPILER Convert

CONVENTIONS. Convert

*UPDATED TO USE NEW PROGRAM CONVERT Convert

KEYWORDS. Convert

*ADDED ENDFILE OPTION TO OPTIONALLY Convert

ALLOW END OF FILE TO BE WRITTEN Convert

VERSION 91-1 (JUNE 1991) *ADDED FORTRAN SAVE OPTION Convert

VERSION 92-1 (JANUARY 1992)*ADDED ACTION OPTION - TO CONTROL Convert

INTERACTIVE INPUT TO CODES Convert

*ADDED BLANK DELIMITED KEYWORD INPUT Convert

(REPLACES EARLIER FIXED FIELD INPUT) Convert

*WARNING...THE INPUT PARAMETER FORMAT Convert

HAS BEEN GENERALIZED - FOR DETAILS Convert

SEE BELOW. Convert

VERSION 94-1 (JANUARY 1994)*VARIABLE PROGRAM FILENAMES Convert

TO ALLOW ACCESS TO FILE STRUCTURES Convert

(WARNING - INPUT PARAMETER FORMAT Convert

HAS BEEN CHANGED) Convert

*CLOSE ALL FILES BEFORE TERMINATING Convert

(SEE, SUBROUTINE ENDIT) Convert

*ADDED KEYWORD CLOSE. Convert

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Convert

*IMPROVED COMPUTER INDEPENDENCE Convert

*ALL DOUBLE PRECISION Convert

*ON SCREEN OUTPUT Convert

VERSION 99-1 (MARCH 1999) *GENERAL IMPROVEMENTS BASED ON Convert

USER FEEDBACK Convert

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Convert

USER FEEDBACK Convert

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Convert

VERS. 2004-1 (MARCH 2004) *GENERAL UPDATE Convert

Convert

OWNED, MAINTAINED AND DISTRIBUTED BY Convert

------------------------------------ Convert

THE NUCLEAR DATA SECTION Convert

INTERNATIONAL ATOMIC ENERGY AGENCY Convert

P.O. BOX 100 Convert

A-1400, VIENNA, AUSTRIA Convert

EUROPE Convert

Convert

ORIGINALLY WRITTEN BY Convert

------------------------------------ Convert

DERMOTT E. CULLEN Convert

UNIVERSITY OF CALIFORNIA Convert

LAWRENCE LIVERMORE NATIONAL LABORATORY Convert

L-159 Convert

P.O. BOX 808 Convert

LIVERMORE, CA 94550 Convert

U.S.A. Convert

TELEPHONE 925-423-7359 Convert

E. MAIL CULLEN1@LLNL.GOV Convert

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Convert

Convert

AUTHORS MESSAGE Convert

--------------- Convert

THE COMMENTS BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENATION Convert

FOR THIS PROGRAM INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ Convert

ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY THE Convert

COMMENTS CONCERNING COMPUTER DEPENDENT CODING. Convert

Convert

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Convert

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Convert

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Convert

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Convert

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Convert

IMPROVE THIS PROGRAM. IN PARTICULAR IF YOUR FORTRAN COMPILER, OR Convert

COMPUTER HAS A SET OF REQUIREMENTS THAT ARE DIFFERENT FROM THOSE Convert

OF CDC, CRAY OR IBM PLEASE NOTIFY THE AUTHOR AND THIS PROGRAM WILL Convert

BE MODIFIED TO CONSIDER YOUR COMPUTER SEPERATELY. HOWEVER, IN Convert

ORDER TO PREVENT A PROLIFERATION OF CODING IT IS IMPERATIVE THAT Convert

YOU IDENTIFY EXACTLY HOW YOUR FORTRAN COMPILER OR COMPUTER DIFFERS Convert

FROM THOSE ALREADY CONSIDERED BY THIS PROGRAM. HOPEFULLY,IN THIS Convert

WAY FUTURE VERSIONS OF THIS PROGRAM WILL BE COMPLETELY COMPATIBLE Convert

FOR USE ON YOUR COMPUTER. Convert

Convert

PURPOSE Convert

------- Convert

THIS PROGRAM IS DESIGNED TO AUTOMATICALLY CONVERT FORTRAN PROGRAMS Convert

FOR USE ON ANY ONE OF A VARIETY OF, Convert

(1) COMPUTERS Convert

(2) COMPILERS Convert

(3) PRECISIONS (SINGLE OR DOUBLE PRECISION) Convert

(4) INSTALLATIONS Convert

(5) STANDARD OR NON-STANDARD FILE NAMES Convert

Convert

FORTRAN CODING CONVENTIONS Convert

-------------------------- Convert

THIS PROGRAM MAY BE USED TO CONVERT ANY PROGRAM WHICH USES THE Convert

FOLLOWING CONVENTIONS. Convert

Convert

ALL FORTRAN STATEMENTS THAT DEPEND ON ANY COMBINATION OF COMPUTER, Convert

COMPILER, PRECISION AND/OR INSTALLATION AND STANDARD FILE NAMES Convert

SHOULD BE PRECEDED AND FOLLOWED BY A COMMENT LINE THAT CONTAINS, Convert

Convert

C***** DOUBLE ****** ACTIVATE DOUBLE PRECISION (DEFAULT) Convert

C***** SINGLE ****** ACTIVATE SINGLE PRECISION Convert

C***** CHARACTER *** TREAT CHARACTER ARRAYS AS CHARACTERS(DEFAULT) Convert

C***** INTEGER ***** TREAT CHARACTER ARRAYS AS INTEGERS Convert

C***** STOP ******** ACTIVATE STOP TO TERMINATE PROGRAM Convert

C***** EXIT ******** ACTIVATE EXIT TO TERMINATE PROGRAM Convert

C***** PROGRAM ***** ACTIVATE PROGRAM LINE AND CONTINUATIONS Convert

C***** NAMES ******* ACTIVATE STANDARD FILENAMES Convert

C***** REWIND ****** ACTIVATE REWIND FILES AT START OF PROGRAM Convert

C***** ENDFILE ***** ACTIVATE ENDFILE AT END OF PROGRAM Convert

C***** CIVIC ******* ACTIVATE LIVERMORE CIVIC COMPILER CONVENTIONS Convert

C***** NOID ******** REMOVE LINE ID IN COLUMNS 73-80 (73-80=BLANK) Convert

C***** SAVE ******** SAVE VARIABLES BETWEEN SUBROUTINE CALLS Convert

C***** ACTION ****** ACTIVATE INTERACTIVE INPUT TO CODES Convert

C***** CLOSE ******* ACTIVATE CLOSE ALL FILES BEFORE TERMINATING Convert

Convert

IF THE USER DOES NOT SELECT, Convert

(1) DOUBLE OR SINGLE - THE PROGRAM WILL ACTIVATE DOUBLE Convert

(2) CHARACTER OR INTEGER - THE PROGRAM WILL ACTIVATE CHARACTER Convert

(3) STOP OR EXIT - THE PROGRAM WILL ACTIVATE STOP Convert

Convert

IF THE USER SELECTS, Convert

(1) DOUBLE AND SINGLE - THE PROGRAM WILL ACTIVATE DOUBLE Convert

(2) CHARACTER AND INTEGER - THE PROGRAM WILL ACTIVATE CHARACTER Convert

(3) STOP AND EXIT - THE PROGRAM WILL ACTIVATE STOP Convert

Convert

IF THE USER DOES NOT SELECT PROGRAM, NAMES, REWIND, ENDFILE, Convert

CIVIC, NOID, SAVE OR ACTION THESE OPTIONS WILL BE TURNED OFF. Convert

Convert

WHERE CODING IS COMPUTER OR COMPILER DEPENDENT CODING WILL BE Convert

PRESENT FOR ALL POSSIBLE OPTIONS. THIS PROGRAM WILL ALLOW THE Convert

THE USER TO CONVERT PROGRAMS FOR USE WITH ANY COMBINATION OF Convert

OPTIONS. FOR EXAMPLES OF HOW THIS CONVENTION IS USED SEE THE Convert

LISTING OF THIS PROGRAM AND THE COMMENTS BELOW ON COMPUTER Convert

DEPENDENT CODING. Convert

Convert

INPUT LINES Convert

----------- Convert

LINE COLS. DESCRIPTION Convert

---- ----- -------------------------------------- Convert

1 1-72 BLANK DELIMITED KEYWORDS Convert

2 1-60 ENDF/B INPUT DATA FILENAME Convert

(STANDARD OPTION = ENDFB.IN) Convert

3 1-60 ENDF/B OUTPUT DATA FILENAME Convert

(STANDARD OPTION = ENDFB.OUT) Convert

Convert

*THE FIRST INPUT LINE IS 72 CHARACTERS. Convert

*KEYWORDS MAY BE LOCATED ANYWHERE WITHIN THESE 72 CHARACTERS Convert

*THERE MAY BE ANY NUMBER OF KEYWORDS INPUT Convert

*EACH KEYWORD MUST BE BLANK DELIMITED, E.G., DOUBLE CHARACTER Convert

IS LEGAL INPUT - DOUBLECHARACTER IS NOT LEGAL INPUT. Convert

*THERE MUST BE ONE OR MORE BLANKS BETWEEN KEYWORDS Convert

Convert

*NOTE, THIS NEW INPUT PARAMETER FORMAT (VERSION 92-1) IS COMPLETELY Convert

COMPATIBLE WITH THE OLDER FIXED FIELD FORMAT. SO THAT IF YOU HAVE Convert

INPUT THAT YOU HAVE USED IN THE PAST YOU CAN CONTINUE TO USE IT. Convert

Convert

LEGAL KEYWORDS INCLUDE, Convert

Convert

DOUBLE ACTIVATE DOUBLE PRECISION (DEFAULT) Convert

SINGLE ACTIVATE SINGLE PRECISION Convert

CHARACTER TREAT CHARACTER ARRAYS AS CHARACTERS(DEFAULT) Convert

INTEGER TREAT CHARACTER ARRAYS AS INTEGERS Convert

PROGRAM ACTIVATE PROGRAM LINE AND CONTINUATIONS Convert

NAMES ACTIVATE STANDARD FILENAMES Convert

REWIND ACTIVATE REWIND FILES AT START OF PROGRAM Convert

ENDFILE ACTIVATE ENDFILE AT END OF PROGRAM Convert

CIVIC ACTIVATE LIVERMORE CIVIC COMPILER CONVENTIONS Convert

NOID REMOVE LINE ID IN COLUMNS 73-80 (73-80=BLANK) Convert

SAVE SAVE VARIABLES BETWEEN SUBROUTINE CALLS Convert

ACTION ACTIVATE INTERACTIVE INPUT FOR CODES Convert

CLOSE ACTIVATE CLOSE ALL FILES BEFORE TERMINATING Convert

Convert

EXAMPLE INPUT NO. 1 Convert

------------------- Convert

TO USE A PROGRAM IN SINGLE PRECISION, USE THE STANDARD FILE NAMES, Convert

REWIND ALL UNITS AT THE START OF THE PROGRAM AND TREAT CHARACTER Convert

ARRAYS AS CHARACTER (FORTRAN-77 CONVENTION). Convert

Convert

READ \PREPRO93\RECENT\RECENT.OLD AND Convert

WRITE \PREPRO93\RECENT\RECENT.NEW Convert

Convert

THE FOLLOWING 3 INPUT LINES ARE REQUIRED, Convert

Convert

SINGLE NAMES REWIND CHARACTER Convert

\PREPRO93\RECENT\RECENT.OLD Convert

\PREPRO93\RECENT\RECENT.NEW Convert

Convert

NOTE, SINCE CHARACTER IS THE STANDARD OPTION THE KEYWORD CHARACTER Convert

NEED NOT APPEAR ON THE ABOVE INPUT LINE. Convert

Convert

EXAMPLE INPUT NO. 2 Convert

------------------- Convert

TO USE A PROGRAM IN DOUBLE PRECISION AND TREAT ALL CHARACTER Convert

ARRAYS AS INTEGER (FORTRAN-H CONVENTION). Convert

Convert

USE THE STANDARD FILENAMES TO READ = CONVERT.IN AND WRITE = Convert

CONVERT.OUT (THIS CAN BE DONE BY LEAVING THE SECOND AND THIRD Convert

INPUT LINES BLANK). Convert

Convert

THE FOLLOWING 3 INPUT LINES ARE REQUIRED, Convert

Convert

DOUBLE INTEGER Convert

(NOTE, THIS IS A BLANK LINE) Convert

(NOTE, THIS IS A BLANK LINE) Convert

Convert

NOTE, SINCE DOUBLE IS THE STANDARD OPTION THE KEYWORD DOUBLE Convert

NEED NOT APPEAR ON THE ABOVE INPUT LINE. Convert

Convert

EXAMPLE INPUT NO. 3 Convert

------------------- Convert

TO ACTIVATE THE PROGRAM LINE, USE DOUBLE PRECISION AND TREAT ALL Convert

CHARACTER ARRAYS AS CHARACTER. Convert

Convert

Convert

READ \PREPRO93\RECENT\RECENT.OLD AND Convert

WRITE THE STANDARD FILENAME = CONVERT.OUT (LEAVE THE THIRD INPUT Convert

LINE BLANK). Convert

Convert

THE FOLLOWING 3 INPUT LINES ARE REQUIRED, Convert

Convert

PROGRAM Convert

\PREPRO93\RECENT\RECENT.OLD Convert

(NOTE, THIS IS A BLANK LINE) Convert

Convert

NOTE, SINCE DOUBLE, CHARACTER AND EXIT ARE THE STANDARD OPTIONS Convert

THEY NEED NOT APPEAR ON THE ABOVE INPUT LINE AND IN THIS EXAMPLE Convert

HAVE BEEN OMITTED. Convert

Convert

WARNING Convert

------- Convert

(1) THE PROGRAM WILL ALWAYS ACTIVATE DOUBLE OR SINGLE, CHARACTER Convert

OR INTEGER (AS DESCRIBED ABOVE). Convert

Convert

(2) CODING IN THE PROGRAM FOR ANY KEYWORDS THAT ARE NOT ACTIVATED Convert

WILL BE CONVERTED TO COMMENT LINES AND AS SUCH WILL EFFECTIVELY Convert

DISAPPEAR FROM THE PROGRAM. THEREFORE IF THE KEYWORDS PROGRAM, Convert

NAMES, REWIND, ENDFILE, CIVIC OR NOID ARE NOT INPUT BY THE USER Convert

THESE OPTIONS WILL BE TURNED OFF AND ANY CODING USING THESE Convert

KEYWORDS WILL EFFECTIVELY DISAPPEAR FROM THE PROGRAM. Convert

Convert

(3) THE SERIES OF CODES THAT ARE DESIGNED TO BE AUTOMATICALLY Convert

TRANSLATED BY THIS PROGRAM REQUIRE THAT ALL CALCULATIONS BE Convert

PERFORMED IN DOUBLE PRECISION ON SHORT WORD LENGTH COMPUTERS Convert

(E.G., IBM COMPUTERS). THIS PROGRAM WILL ALLOW YOU TO SPECIFY Convert

EITHER DOUBLE OR SINGLE PRECISION. HOWEVER, IF YOU SPECIFY Convert

SINGLE PRECISION THIS PROGRAM WILL PRINT A WARNING MESSAGE THAT Convert

THE CONVERTED PROGRAM SHOULD ONLY BE USED ON LONG WORD LENGTH Convert

COMPUTERS (E.G., CDC COMPUTERS). Convert

Convert

PROGRAM OPERATION Convert

----------------- Convert

THE PROGRAM WILL SEARCH FOR COMMENT LINES THAT START WITH C** Convert

IN COLUMNS 1-3 FOLLOWED BY ANY ONE OF THE ALLOWED KEYWORDS Convert

IF THE KEYWORD IS THE SAME AS ONE OF THE KEYWORDS INPUT BY Convert

THE USER ALL LINES UP TO THE NEXT LINE WITH C** IN COLUMNS 1-3 Convert

FOLLOWED BY THE SAME KEYWORD WILL BE SET ACTIVE BY SETTING COLUMN Convert

1 TO BLANK. IF THE KEYWORDS DIFFERS FROM THAT INPUT BY THE USER Convert

ALL LINES UP TO THE NEXT LINE WITH C** IN COLUMNS 1-3 FOLLOWED BY Convert

THE SAME KEYWORD WILL BE SET INACTIVE BY SETTING COLUMN 1 TO C. Convert

Convert

KEYWORDS MAY NOT BE NESTED (I.E., THIS PROGRAM WILL ONLY OPERATE Convert

PROPERLY IF KEYWORDS APPEAR IN PAIRS. ONCE A LINE IS FOUND THAT Convert

CONTAINS A KEYWORD, THE NEXT LINE THAT CONTAINS A KEYWORD MUST Convert

CONTAIN THE SAME KEYWORD). Convert

Convert

PROGRAM LINE Convert

------------ Convert

THE FORTRAN FILE MAY START WITH A PROGRAM LINE AND CONTINUATIONS. Convert

FOR USE ON CDC-7600 OR CRAY-1 COMPUTERS THIS PROGRAM CAN ACTIVATE Convert

THE PROGRAM LINE AND CONTINUATION LINES. FOR USE ON OTHER TYPES OF Convert

COMPUTERS THIS PROGRAM WILL AUTOMATICALLY DE-ACTIVATE THE PROGRAM Convert

LINE AND CONTINUATION LINES. THIS CONVENTIONS HAS BEEN INTRODUCED Convert

BECAUSE SOME CDC-7600 COMPILERS CONSIDER IT AN ERROR IF THE FIRST Convert

LINE IS NOT A PROGRAM LINE. PRECEEDING COMMENT LINES ARE NOT Convert

ALLOWED. THEREFORE THE NORMAL CONVENTION, DESCRIBED ABOVE, OF Convert

USING PRECEDING AND FOLLOWING COMMENT LINES, CANNOT BE USED AT Convert

THE BEGINNING OF THE PROGRAM. Convert

Convert

COMMENT LINES Convert

------------- Convert

COMMENT LINES MAY APPEAR ON LINES BETWEEN PAIRS OF KEYWORD LINES Convert

ONLY IF THE COMMENT LINES CONTAINS C-- IN COLUMS 1-3. ANY LINE Convert

THAT CONTAINS ANYTHING ELSE IN COLUMNS 1-3 MAY BE ACTIVATED Convert

BY THIS PROGRAM BY SETTING COLUMN 1 BLANK AND CAN LEAD TO ERRORS Convert

DURING COMPILATION AND/OR EXECUTION. Convert

Convert

INPUT FILES Convert

----------- Convert

UNIT DESCRIPTION Convert

---- ----------- Convert

2 INPUT LINE (BCD - 80 CHARACTERS/RECORD) Convert

10 ORIGINAL PROGRAM (BCD - 80 CHARACTERS/RECORD) Convert

Convert

OUTPUT FILES Convert

------------ Convert

UNIT DESCRIPTION Convert

---- ----------- Convert

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Convert

11 RE-FORMATTED PROGRAM (BCD - 80 CHARACTERS/RECORD) Convert

Convert

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Convert

--------------------------------------------------------------- Convert

UNIT FILE NAME Convert

---- ---------- Convert

2 CONVERT.INP Convert

3 CONVERT.LST Convert

10 CONVERT.IN Convert

11 CONVERT.OUT Convert

Convert

======================================================================= Convert

======================================================================= Dictin

Dictin

PROGRAM DICTIN (Renamed from DICTION to eliminate conflict with Dictin

UNIX diction command - 12/22/02) Dictin

============== Dictin

VERSION 81-1 (SEPTEMBER 1981) Dictin

VERSION 82-1 (JANUARY 1982) Dictin

VERSION 83-1 (JANUARY 1983) *KEEP ORIGINAL MOD. NUMBER Dictin

*NEW, MORE COMPATIBLE I/O UNITS. Dictin

VERSION 84-1 (SEPTEMBER 1984)*UPDATED TO HANDLE ENDF/B-VI FORMAT. Dictin

(PROGRAM WILL NOW WORK ON ALL Dictin

VERSIONS OF THE ENDF/B FORMAT). Dictin

VERSION 85-1 (AUGUST 1985) *FORTRAN-77/H VERSION Dictin

VERSION 86-1 (JANUARY 1986) *MAT ORDER CHECK. Dictin

*IF NO HOLLERITH SECTION COPY MAT. Dictin

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Dictin

FILE NAMES (SEE, SUBROUTINE FILEIO Dictin

FOR DETAILS). Dictin

*IMPROVED BASED ON USER COMMENTS. Dictin

VERSION 89-1 (JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO Dictin

INSURE PROGRAM WILL NOT DO ANYTHING Dictin

CRAZY. Dictin

*IMPROVED BASED ON USER COMMENTS. Dictin

*ADDED LIVERMORE CIVIC COMPILER Dictin

CONVENTIONS. Dictin

*UPDATED TO USE NEW PROGRAM CONVERT Dictin

KEYWORDS. Dictin

VERSION 92-1 (JANUARY 1992) *UPDATED BASED ON USER COMMENTS. Dictin

*UP TO 6000 SECTIONS PER TAPE. Dictin

*CHANGED DEFAULT MOD NUMBER FOR NEW Dictin

SECTIONS FROM 0 TO 1 Dictin

VERSION 94-1 (JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES Dictin

TO ALLOW ACCESS TO FILE STRUCTURES Dictin

(WARNING - INPUT PARAMETER FORMAT Dictin

HAS BEEN CHANGED) Dictin

*CLOSE ALL FILES BEFORE TERMINATING Dictin

(SEE, SUBROUTINE ENDIT) Dictin

*ADDED FORTRAN SAVE OPTION Dictin

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Dictin

*IMPROVED COMPUTER INDEPENDENCE Dictin

*ALL DOUBLE PRECISION Dictin

*ON SCREEN OUTPUT Dictin

*UNIFORM TREATMENT OF ENDF/B I/O Dictin

*IMPROVED OUTPUT PRECISION Dictin

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Dictin

POINT READ FOR MORE DIGITS Dictin

*UPDATED TEST FOR ENDF/B FORMAT Dictin

VERSION BASED ON RECENT FORMAT CHANGE Dictin

*GENERAL IMPROVEMENTS BASED ON Dictin

USER FEEDBACK Dictin

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Dictin

USER FEEDBACK Dictin

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Dictin

*RENAMED dictin TO ELIMINATE CONFLICT Dictin

WITH UNIX diction COMMAND. Dictin

*ADDED DOCUMENTATION LINE TO COMMENTS. Dictin

VERS. 2004-1 (JAN. 2004) *GENERAL UPDATE BASED ON USER FEEDBACK Dictin

*UP TO 100,000 SECTIONS PER TAPE. Dictin

Dictin

OWNED, MAINTAINED AND DISTRIBUTED BY Dictin

------------------------------------ Dictin

THE NUCLEAR DATA SECTION Dictin

INTERNATIONAL ATOMIC ENERGY AGENCY Dictin

P.O. BOX 100 Dictin

A-1400, VIENNA, AUSTRIA Dictin

EUROPE Dictin

Dictin

ORIGINALLY WRITTEN BY Dictin

------------------------------------ Dictin

DERMOTT E. CULLEN Dictin

UNIVERSITY OF CALIFORNIA Dictin

LAWRENCE LIVERMORE NATIONAL LABORATORY Dictin

L-159 Dictin

P.O. BOX 808 Dictin

LIVERMORE, CA 94550 Dictin

U.S.A. Dictin

TELEPHONE 925-423-7359 Dictin

E. MAIL CULLEN1@LLNL.GOV Dictin

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Dictin

Dictin

AUTHORS MESSAGE Dictin

--------------- Dictin

THE COMMENTS BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENATION Dictin

FOR THIS PROGRAM INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ Dictin

ALL OF THESE COMMENTS BEFORE IMPLEMENTATION. Dictin

Dictin

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Dictin

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Dictin

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Dictin

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Dictin

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Dictin

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Dictin

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Dictin

COMPUTER. Dictin

Dictin

PURPOSE Dictin

------- Dictin

THIS PROGRAM IS DESIGNED TO CREATE A REACTION INDEX FOR EACH Dictin

MATERIAL ON AN ENDF/B FORMATTED TAPE AND TO INSERT THIS REACTION Dictin

INDEX IN FILE 1, SECTION 451 OF EACH MATERIAL. Dictin

Dictin

IN THE DESCRIPTION THAT FOLLOWS FOR SIMPLICITY THE ENDF/B Dictin

TERMINOLOGY---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL Dictin

MEDIUM MAY BE TAPE, CARDS, DISK, OR ANY OTHER MEDIUM. Dictin

Dictin

ENDF/B FORMAT Dictin

------------- Dictin

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Dictin

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Dictin

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Dictin

Dictin

THIS PROGRAM WILL AUTOMATICALLY DETERMINE WHICH VERSION OF THE Dictin

ENDF/B FORMAT EACH MAT IS IN AND WILL THEN PROPERLY REPLACE THE Dictin

REACTION INDEX FOR EACH MAT. DIFFERENT MATS ON THE SAME TAPE MAY Dictin

EVEN BE IN DIFFERENT VERSIONS OF THE ENDF/B FORMAT. Dictin

Dictin

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Dictin

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Dictin

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Dictin

NUMBERS (COLUMNS 76-80) NEED NOT BE PRESENT ON INPUT, BUT WILL BE Dictin

CORRECTLY OUTPUT ON ALL LINES. Dictin

Dictin

ENDF/B FORMAT VERSION Dictin

--------------------- Dictin

THE ENDF/B FORMAT CAN BE DETERMINED FROM THE SECOND LINE OF Dictin

THE HOLLERITH SECTION (MF=1, MT=451). Dictin

ENDF/B-IV = N1 - LINE COUNT (POSITIVE) Dictin

ENDFB/-V = N1 = N2 =0 Dictin

ENDF/B-VI = N1 =0, N2= VERSION NUMBER (6 OR MORE) Dictin

Dictin

SECTION SIZE Dictin

------------ Dictin

SINCE THIS PROGRAM ONLY READS THE DATA ONE LINE AT A TIME THERE Dictin

IS NO LIMIT TO THE SIZE OF ANY GIVEN SECTION, E.G. THE TOTAL Dictin

CROSS SECTION MAY BE DESCRIBED BY 200,000 DATA POINTS. Dictin

Dictin

NUMBER OF SECTIONS PER TAPE Dictin

--------------------------- Dictin

IT IS ASSUMED THAT THE ENDF/B TAPE CONTAINS 100,000 OR FEWER Dictin

SECTIONS = 100,000 OR FEWER MAT,MF,MT COMBINATIONS. IF THIS LIMIT Dictin

IS EXCEEDED THIS PROGRAM WILL TERMINATE EXECUTION. IF NEED BE THIS Dictin

LIMIT CAN EASILY BE CHANGED BY CHANGING THE DIMENSION STATEMENT Dictin

BELOW AND RE-DEFINING THE VARIABLE MAXTAB IN THE BELOW DATA Dictin

STATEMENT. ALTERNATIVELY THE ENDF/B TAPE MAY BE DIVIDED INTO A Dictin

NUMBER SMALLER TAPES EACH CONTAINING 100,000 OR FEWER SECTIONS. Dictin

EACH ENDF/B TAPE CAN THEN RUN THROUGH THIS PROGRAM AND THE OUTPUT Dictin

FOR EACH ENDF/B TAPE CAN THEN BE RE-COMBINED (I.E., MERGED BACK Dictin

TOGETHER). Dictin

Dictin

HOLLERITH SECTION Dictin

----------------- Dictin

IF ANY MATERIAL DOES NOT INITIALLY CONATIN A SECTION MF=1, MT=451 Dictin

A WARNING MESSAGE WILL BE PRINTED AND THE MATERIAL WILL BE COPIED. Dictin

Dictin

IF ANY MATERIAL INITIALLY CONTAINS A SECTION MF=1, MT=451 A NEW Dictin

REACTION INDEX WILL BE CREATED AND INSERTED. THE INITIAL SECTION Dictin

MF=1, MT=451 MAY OR MAY NOT CONTAIN A REACTION INDEX. Dictin

Dictin

IF THE MATERIAL INITIALLY CONTAINS A REACTION INDEX IT WILL BE Dictin

USED TO DEFINE THE MOD NUMBER FOR CORRESPONDING SECTIONS IN THE Dictin

NEW REACTION INDEX (I.E. IF A SECTION FROM THE ORIGINAL REACTION Dictin

INDEX HAS THE SAME MF/MT NUMBERS AS A SECTION IN THE NEW REACTION Dictin

INDEX THE MOD NUMBER FROM THE ORIGINAL REACTION INDEX WILL BE USED Dictin

IN THE NEW REACTION INDEX). OTHERWISE THE MOD NUMBER IN THE NEW Dictin

REACTION INDEX WILL BE SET EQUAL TO ZERO. Dictin

Dictin

PROGRAM OPERATION Dictin

----------------- Dictin

THE ENTIRE ENDF/B TAPE IS FIRST READ AND A DICTIONARY ENTRY IS Dictin

CREATED FOR EACH SECTION OF THE TAPE. THE ENDF/B TAPE IS THEN Dictin

REWOUND AND READ A SECOND TIME. DURING THIS SECOND PASS THE Dictin

DICTIONARY OF EACH MAT IS REPLACED. THIS VERSION OF DICTIN Dictin

DOES NOT USE SCRATCH FILES AND IS MORE EFFICIENT THAN EARLIER Dictin

VERSIONS OF DICTIN. Dictin

Dictin

INPUT LINES Dictin

----------- Dictin

LINE COLS. DESCRIPTION Dictin

---- ----- ------------------------------ Dictin

1 1-60 ENDF/B INPUT DATA FILENAME Dictin

(STANDARD OPTION = ENDFB.IN) Dictin

2 1-60 ENDF/B OUTPUT DATA FILENAME Dictin

(STANDARD OPTION = ENDFB.OUT) Dictin

Dictin

EXAMPLE INPUT NO. 1 Dictin

------------------- Dictin

READ \ENDFB6\K300\ENDFB.IN AND WRITE \ENDFB\K300\ENDFB.OUT. THE Dictin

FOLLOWING 2 INPUT LINES ARE REQUIRED, Dictin

Dictin

\ENDFB6\K300\ENDFB.IN Dictin

\ENDFB6\K300\ENDFB.OUT Dictin

Dictin

EXAMPLE INPUT NO. 2 Dictin

------------------- Dictin

USE THE DEFAULT FILENAMES TO READ ENDFB.IN AND WRITE ENDFB.OUT. Dictin

2 BLANK INPUT LINES ARE REQUIRED Dictin

Dictin

INPUT FILES Dictin

----------- Dictin

UNIT DESCRIPTION Dictin

---- ----------- Dictin

2 INPUT PARAMETERS (BCD - 80 CHARACTERS/RECORD) Dictin

10 ORIGINAL TAPE OF ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Dictin

Dictin

OUTPUT FILES Dictin

------------ Dictin

UNIT DESCRIPTION Dictin

---- ----------- Dictin

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Dictin

11 FINAL TAPE OF ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Dictin

Dictin

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Dictin

--------------------------------------------------------------- Dictin

UNIT FILE NAME Dictin

---- ---------- Dictin

2 DICTIN.INP Dictin

3 DICTIN.LST Dictin

10 ENDFB.IN Dictin

11 ENDFB.OUT Dictin

Dictin

======================================================================= Dictin

======================================================================= Evalplot

Evalplot

PROGRAM EVALPLOT Evalplot

VERSION 75-1 (AUGUST 1975) Evalplot

VERSION 76-1 (JULY 1976) Evalplot

VERSION 77-1 (APRIL 1977) Evalplot

VERSION 78-1 (JULY 1978) Evalplot

VERSION 79-1 (FEBRUARY 1979) Evalplot

VERSION 80-1 (JULY 1980) *IBM VERSION Evalplot

VERSION 80-2 (DECEMBER 1980) Evalplot

VERSION 81-1 (MARCH 1981) Evalplot

VERSION 81-2 (AUGUST 1981) *IMPROVED ZOOM CAPABILITY Evalplot

VERSION 82-1 (JANUARY 1982) *IMPROVED COMPUTER COMPATIBILITY Evalplot

VERSION 83-1 (JANUARY 1983) *ELIMINATED COMPUTER DEPENDENT CODING. Evalplot

VERSION 83-2 (OCTOBER 1983) *ADDED PLOTTING OF HISTOGRAM DATA. Evalplot

VERSION 84-1 (DECEMBER 1984)*ADDED PLOTS OF LEGENDRE COEFFICENTS Evalplot

AS A FUNCTION OF ENERGY. Evalplot

*ADDED SMALL PLOTTING MODE. Evalplot

VERSION 85-1 (AUGUST 1985) *FORTRAN-77/H VERSION Evalplot

VERSION 86-1 (JANUARY 1986) *ENDF/B-VI FORMAT Evalplot

VERSION 88-1 (JULY 1988) *MAJOR REVISION TO MAKE CODE EASILY Evalplot

INTERFACEABLE TO ALMOST ANY PLOTTER. Evalplot

*WARNING...INPUT PARAMETERS FROM BEEN Evalplot

CHANGED (SEE, DESCRIPTION BELOW) Evalplot

*COMPUTER INDEPENDENT SOFTWARE Evalplot

CHARACTERS. Evalplot

*COLOR PLOTS. Evalplot

*MT NUMBER DEFINITIONS FROM DATA FILE Evalplot

READ BY PROGRAM Evalplot

*FORTRAN-77 REQUIRED (FORTRAN-H NO Evalplot

SUPPORTED BY THIS PROGRAM). Evalplot

*OPTION...INTERNALLY DEFINE ALL I/O Evalplot

FILE NAMES (SEE, SUBROUTINE FILEIO Evalplot

FOR DETAILS). Evalplot

*IMPROVED BASED ON USER COMMENTS. Evalplot

VERSION 89-1 (JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO Evalplot

INSURE PROGRAM WILL NOT DO ANYTHING Evalplot

CRAZY. Evalplot

*UPDATED TO USE NEW PROGRAM CONVERT Evalplot

KEYWORDS. Evalplot

*ADDED LIVERMORE CIVIC COMPILER Evalplot

CONVENTIONS. Evalplot

*FORTRAN-77/FORTRAN-H COMPATIBLE Evalplot

*SPECIAL ENDF/B MATERIAL DEFINITIONS Evalplot

(ZA.LT.1000) FROM DATA FILE READ Evalplot

BY PROGRAM. Evalplot

VERSION 89-2 (MARCH 1989) *ADDED ENDF/B-V AND VI MT Evalplot

DEFINITIONS. PROGRAM WILL DETERMINE Evalplot

ENDF/B FORMAT BASED ON MF=1, Evalplot

MT=451 AND USE ASPPROPRIATE MT Evalplot

DEFINITIONS. IF NO MF=1, MT=451 Evalplot

PROGRAM WILL USE ENDF/B-V Evalplot

MT DEFINITIONS. Evalplot

VERSION 89-3 (JUNE 1989) *3 CHARACTER FONTS Evalplot

VERSION 92-1 (JANUARY 1992) *COMPLETE REWRITE OF CODE Evalplot

*ADDED PHOTON DATA, MF=23 AND 27 Evalplot

*ADDED INCIDENT CHARGED PARTICLES Evalplot

(IDENTIFIED IN PLOT TITLES) Evalplot

*ADDED FORTRAN SAVE OPTION. Evalplot

*UPDATED BASED ON USER COMMENTS Evalplot

*ADDED RETRIEVAL BY UP TO 100 Evalplot

MAT/MF/MT OR ZA/MF/MT RANGES Evalplot

*WARNING...INPUT PARAMETER FORMAT Evalplot

HAS BEEN CHANGED...SEE DESCRIPTION Evalplot

BELOW. Evalplot

VERSION 92-2 (FEBRUARY 1992)*ADDED PHOTON SPECTRA, MF=15. Evalplot

*ADDED MULTIPLICATION OF DISTRIBUTIONS Evalplot

IN MF=5 AND 15 BY PROBABILITY=YIELD. Evalplot

*INCREASED PAGE SIZE TO 12000 POINTS Evalplot

VERSION 92-3 (MAY 1992) *CORRECTED DESCRIPTION OF INPUT Evalplot

PARAMETERS AND EXAMPLE PROBLEMS. Evalplot

*CORRECTED FOR ENDF/B-VI DEFINITION OF Evalplot

TEMPERATURE FROM MF=1/MT=451. Evalplot

*CORRECTED LOGIC SO THAT EACH REQUEST Evalplot

IS TREATED SEPARATELY TO CREATE A Evalplot

PLOT, UNLESS REQUESTS ARE CHAINED Evalplot

TOGETHER. Evalplot

*ADDED VARIABLE CHARACTER SIZE INPUT. Evalplot

VERSION 93-1 (MARCH 1993) *INCREASED PAGE SIZE FROM 12000 Evalplot

TO 210000 Evalplot

*INCREASED THE NUMBER OF ENERGIES Evalplot

VS. LEGENDRE COEFFICIENTS FROM Evalplot

167 TO 7000 Evalplot

*UPDATED FOR ON SCREEN GRAPHICS Evalplot

USING THE LAHEY FORTRAN COMPILER. Evalplot

VERSION 94-1 (JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES Evalplot

TO ALLOW ACCESS TO FILE STRUCTURES Evalplot

(WARNING - INPUT PARAMETER FORMAT Evalplot

HAS BEEN CHANGED) Evalplot

*CLOSE ALL FILES BEFORE TERMINATING Evalplot

(SEE, SUBROUTINE ENDIT) Evalplot

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Evalplot

*IMPROVED COMPUTER INDEPENDENCE Evalplot

*ALL DOUBLE PRECISION Evalplot

*UNIFORM TREATMENT OF ENDF/B I/O Evalplot

*IMPROVED OUTPUT PRECISION Evalplot

*DEFINED SCRATCH FILE NAMES Evalplot

*ALL DOUBLE PRECISION Evalplot

VERSION 97-1 (APRIL 1997) *INCREASED PAGE SIZE FROM 210000 Evalplot

TO 480,000 Evalplot

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Evalplot

POINT READ FOR MORE DIGITS Evalplot

*UPDATED TEST FOR ENDF/B FORMAT Evalplot

VERSION BASED ON RECENT FORMAT CHANGE Evalplot

*GENERAL IMPROVEMENTS BASED ON Evalplot

USER FEEDBACK Evalplot

VERS. 2000-1 (FEBRUARY 2000)*ADDED MF=10, ACTIVATION CROSS Evalplot

SECTION PLOTS. Evalplot

*INCREASED DIMENSIONS TO HANDLE MORE Evalplot

SECTIONS - UP TO 1,000 Evalplot

*GENERAL IMPROVEMENTS BASED ON Evalplot

USER FEEDBACK Evalplot

VERS. 2002-1 (Nov. 2002) *OPTIONAL INPUT PARAMETERTS Evalplot

*OPTIONAL BLACK OR WHITE BACKGROUND Evalplot

*COLOR POSTSCRIPT FILES Evalplot

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Evalplot

*INCREASED PAGE SIZE TO 600,000 Evalplot

*INCREASED THE NUMBER OF ENERGIES Evalplot

VS. LEGENDRE COEFFICIENTS FROM Evalplot

7000 TO 20000 Evalplot

Evalplot

OWNED, MAINTAINED AND DISTRIBUTED BY Evalplot

------------------------------------ Evalplot

THE NUCLEAR DATA SECTION Evalplot

INTERNATIONAL ATOMIC ENERGY AGENCY Evalplot

P.O. BOX 100 Evalplot

A-1400, VIENNA, AUSTRIA Evalplot

EUROPE Evalplot

Evalplot

ORIGINALLY WRITTEN BY Evalplot

------------------------------------ Evalplot

DERMOTT E. CULLEN Evalplot

UNIVERSITY OF CALIFORNIA Evalplot

LAWRENCE LIVERMORE NATIONAL LABORATORY Evalplot

L-159 Evalplot

P.O. BOX 808 Evalplot

LIVERMORE, CA 94550 Evalplot

U.S.A. Evalplot

TELEPHONE 925-423-7359 Evalplot

E. MAIL CULLEN1@LLNL.GOV Evalplot

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Evalplot

Evalplot

AUTHORS MESSAGE Evalplot

--------------- Evalplot

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Evalplot

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Evalplot

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Evalplot

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY Evalplot

THE COMMENTS CONCERNING MACHINE DEPENDENT CODING. Evalplot

Evalplot

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Evalplot

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Evalplot

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Evalplot

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Evalplot

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Evalplot

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Evalplot

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Evalplot

COMPUTER. Evalplot

Evalplot

PURPOSE Evalplot

------- Evalplot

THIS PROGRAM IS DESIGNED TO READ EVALUATED DATA FROM THE ENDF/B Evalplot

FORMAT AND TO PLOT THE DATA. THE USER MAY SELECT CROSS SECTIONS, Evalplot

PARAMETERS (E.G. NU-BAR, MU-BAR, ETC.), ANGULAR DISTRIBUTIONS Evalplot

AND/OR ENERGY DISTRIBUTIONS TO BE PLOTTED. Evalplot

Evalplot

IN THE FOLLOWING FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B Evalplot

TAPE--WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS, Evalplot

DISK OR ANY OTHER MEDIUM. Evalplot

Evalplot

ON WHAT COMPUTERS WILL THE PROGRAM RUN Evalplot

------------------------------------------------------------------ Evalplot

THE PROGRAM HAS BEEN IMPLEMENTED ON A WIDE VARIETY OF COMPUTERS Evalplot

FROM THE ONE EXTREME OF LARGE MAINFRAME CRAY AND IBM COMPUTERS Evalplot

TO THE OTHER EXTREME OF SUN TERMINALS AND IBM PERSONAL COMPUTERS. Evalplot

THE PROGRAM IS DESIGNED TO RUN ON VIRTUALLY ANY COMPUTER. FOR Evalplot

SPECIAL CONSIDERATIONS SEE THE SECTIONS BELOW ON, Evalplot

(1) COMPUTER DEPENDENT CODING Evalplot

(2) PLOTTER/GRAPHICS TERMINAL INTERFACE Evalplot

Evalplot

ON WHAT PLOTTERS WILL THE PROGRAM RUN Evalplot

------------------------------------------------------------------ Evalplot

THE PLOTTER MAY USE UNITS OF INCHES, CENTIMETERS, MILLIMETERS, Evalplot

VIRTUALLY ANYTHING. INTERNALLY THE PROGRAM WILL DEFINE PLOTS IN Evalplot

APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. AS PART OF THE Evalplot

INPUT THE USER DEFINES THE ACTUAL SIZE OF THE PLOT IN THE UNITS Evalplot

(I.E., INCHES, CENTIMETERS, MILLIMETERS, WHATEVER) OF THE REAL Evalplot

PLOT. THE PLOT IS TRANSFORMED TO THE SIZE OF THE LOCAL PLOTTER Evalplot

AND OUTPUT. USING THIS CONVENTION THIS PROGRAM SHOULD BE EASY Evalplot

TO INTERFACE TO VIRTUALLY ANY PLOTTER OR GRAPHICS TERMINAL. Evalplot

Evalplot

GRAPHICS INTERFACE Evalplot

------------------------------------------------------------------ Evalplot

THIS PROGRAM USES A SIMPLE CALCOMP LIKE GRAPHICS INTERFACE WHICH Evalplot

REQUIRES ONLY 3 SUBROUTINES...PLOTS, PLOT AND PEN (DESCRIBED IN Evalplot

DETAIL BELOW). ALL CHARACTERS AND SYMBOLS ARE DRAWN USING TABLES Evalplot

OF PEN STROKES (SUPPLIED WITH THIS PROGRAM). USING THIS METHOD Evalplot

THE PROGRAM SHOULD BE SIMPLE TO INTERFACE TO VIRTUALLY ANY PLOTTER Evalplot

OR GRAPHICS TERMINAL AND THE APPEARANCE AND LAYOUT OF THE PLOTS Evalplot

SHOULD BE INDEPENDENT OF WHICH PLOTTER IS USED. Evalplot

Evalplot

PROGRAM IDENTIFICATION Evalplot

---------------------- Evalplot

AS DISTRIBUTED THE FIRST FRAME OF PLOTTED OUTPUT WILL DOCUMENT Evalplot

THE PROGRAM NAME, VERSION AND INSTALLATION. THIS INFORMATION IS Evalplot

STORED AS DATA IN THE ARRAY VERSES NEAR THE BEGINNING OF Evalplot

SUBROUTINE FRAME1. IF YOU WISH TO CUSTOMIZE THE OUTPUT TO IDENTIFY Evalplot

YOUR INSTALLATION CHANGE THE LAST TWO LINES OF THE ARRAY VERSES. Evalplot

Evalplot

SIZE OF PLOTS Evalplot

------------- Evalplot

THE PROGRAM HAS A BUILT-IN DEFAULT SIZE TO MAKE EACH PLOT 13.50 Evalplot

BY 10.24 INCHES. THIS SIZE WAS SELECTED ASSUMING THAT THE Evalplot

RESOLUTION OF THE PLOTTER IS 1024 RASTER POINTS PER INCH. THE Evalplot

USER MAY CHANGE THE SIZE OF THE PLOT BY SPECIFYING ANY REQUIRED Evalplot

SIZE ON THE FIRST INPUT LINE. IN PARTICULAR FOR USE ON ANY PLOTTER Evalplot

THAT USES CENTIMETERS INSTEAD OF INCHES THE USER MAY MERELY Evalplot

SPECIFY THE REQUIRED SIZE OF THE PLOT IN CENTIMETERS (E.G., TO Evalplot

OBTAIN A 13.50 BY 10.24 INCH PLOT, THE USER NEED ONLY SPECIFY Evalplot

34.3 BY 26 ON THE FIRST INPUT LINE...ASSUMING 2.54 CENTIMETERS PER Evalplot

INCH, OR 343 BY 260 FOR MILLIMETERS..ASSUMING 25.4 MILLIMETERS Evalplot

PER INCH). Evalplot

Evalplot

CHARACTER SIZE Evalplot

-------------- Evalplot

THE PLOT HAS A BUILT-IN CHARACTER SIZE WHICH HAS BEEN DEFINED FOR Evalplot

COMPATIBILITY WITH THE BUILT-IN PLOT SIZE. IF THE USER SPECIFIES Evalplot

BY INPUT A DIFFERENT PLOT SIZE, THE PROGRAM WILL AUOTMATICALLY Evalplot

SCALE THE SIZE OF ALL CHARACTERS BY THE RATIO OF THE Y SIZE OF THE Evalplot

PLOT SPECIFIED BY THE USER TO THE BUILT-IN Y SIZE OF PLOTS (E.G., Evalplot

FOR PLOTS WHICH ARE ONLY 5.12 HIGH (Y DIRECTION) ALL CHARACTERS Evalplot

WILL BE SCALED TO BE ONLY 1/2 THE CHARACTER SIZE ON PLOTS WHICH Evalplot

ARE 10.24 HIGH (10.24 = THE BUILT-IN SIZE). NOTE, CHANGES IN THE Evalplot

X SIZE OF THE PLOT WILL NOT HAVE ANY EFFECT ON THE CHARACTER SIZE Evalplot

(E.G., FOR A LONG PLOT, 30 BY 10.24 THE CHARACTER SIZE WILL BE THE Evalplot

THE SAME AS ON A 13.50 BY 10.24 PLOT). Evalplot

Evalplot

PLOT PER FRAME Evalplot

-------------- Evalplot

BY INPUT THE USER CAN SPECIFY NOT ONLY THE ACTUAL SIZE OF THE Evalplot

LOCAL PLOTTER, BUT ALSO HOW MANY PLOTS SHOULD APPEAR ON EACH Evalplot

FRAME. THIS IS DONE BY SPECIFYING THE LAYOUT OF A FRAME IN TERMS Evalplot

OF THE NUMBER OF PLOTS IN THE X AND Y DIRECTION. FOR EXAMPLE BY Evalplot

SPECIFYING THAT EACH FRAME BE DIVIDED INTO 3 PLOTS IN THE X Evalplot

DIRECTION AND 2 PLOTS IN THE Y DIRECTION, EACH FRAME WILL CONTAIN Evalplot

UP TO 6 PLOTS (3 X 2). INTERNALLY EACH PLOT WILL BE GENERATED TO Evalplot

STANDARD A4 SIZE, AS DESCRIBED ABOVE, AND THEN ON OUTPUT SCALED Evalplot

TO THE NUMBER OF PLOTS PER FRAME SPECIFIED BY THE USER INPUT. Evalplot

Evalplot

ENDF/B FORMAT Evalplot

------------- Evalplot

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Evalplot

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Evalplot

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Evalplot

Evalplot

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Evalplot

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Evalplot

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Evalplot

NUMBERS (COLUMNS 76-80) ARE IGNORED. FORMAT OF SECTION MT=452, 455 Evalplot

OF MF=1, AND ALL SECTIONS OF MF=3, 4 AND 5 MUST BE CORRECT. ALL Evalplot

OTHER SECTION OF DATA ARE SKIPPED AND AS SUCH THE OPERATION OF Evalplot

THIS PROGRAM IS INSENSITIVE TO THE CORRECTNESS OR INCORRECTNESS Evalplot

OF ALL OTHER SECTIONS. Evalplot

Evalplot

INTERPOLATION LAW Evalplot

----------------- Evalplot

EACH TABLE OF DATA MAY USE EITHER COMPLETELY HISTOGRAM OR Evalplot

COMPLETELY LINEAR INTERPOLATION LAW (THE TWO INTERPOLATION LAWS Evalplot

CANNOT BE MIXED TOGETHER IN ONE TABLE). EITHER OF THESE TWO Evalplot

REPRESENTATIONS WILL BE STORED IN CORE IN LINEARLY INTERPOLABLE Evalplot

FORM. IF THIS PROGRAM FINDS ANY DATA THAT USES ANY OTHER Evalplot

INTERPOLATION LAW IT WILL PRINT AN ERROR MESSAGE AND PLOT THE Evalplot

TABLE AS IF IT WERE LINEARLY INTERPOLABLE. THE ONLY ERROR THAT Evalplot

WILL RESULT IN THE PLOT WILL BE IN THE CURVE FOLLOWED BETWEEN Evalplot

TABULATED POINTS. PROGRAM LINEAR (UCRL-50400, VOL. 17, PART A) Evalplot

MAY BE USED TO CONVERT CROSS SECTIONS TO LINEARLY INTERPOLABLE Evalplot

FORM. PROGRAM LEGEND CAN BE USED FOR ANGULAR DISTRIBUTIONS AND Evalplot

PROGRAM ENERGY CAN BE USED FOR SECONDARY ENERGY DISTRIBUTIONS. Evalplot

Evalplot

REACTION INDEX Evalplot

-------------- Evalplot

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Evalplot

SECTION MF=1, MT=451 OF EACH EVALUATION. Evalplot

Evalplot

PAGE SIZE Evalplot

--------- Evalplot

ONLY ONE PAGE OF DATA = 600000 DATA POINTS - IS KEPT IN CORE AT Evalplot

ANY GIVEN TIME. IF THERE IS MORE THAN THIS MANY POINTS THEY WILL Evalplot

BE KEPT ON A SCRATCH FILE AND LOADED INTO CORE AS NEEDED. Evalplot

Evalplot

TO CHANGE THE PAGE SIZE, Evalplot

Evalplot

1) CHANGE 600000 TO THE NEW PAGE SIZE Evalplot

2) CHANGE 1200000 TO TWO TIMES THE NEW PAGE SIZE Evalplot

Evalplot

SECTION SIZE Evalplot

------------ Evalplot

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Evalplot

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Evalplot

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Evalplot

Evalplot

THE ONLY EXCEPTION TO THIS RULE IS THAT EACH TABLE OF DATA WHICH Evalplot

USES A HISTOGRAM INTERPOLATION LAW CANNOT EXCEED HALF THE SIZE Evalplot

OF THE IN CORE PAGE (PRESENTLY 600000/2=300000) WHICH IS ADEQUATE Evalplot

FOR ALMOST ALL HISTOGRAM (E.G. MULTIGROUP) REPRESENTATIONS OF Evalplot

A SINGLE TABLE (E.G. REACTION). Evalplot

Evalplot

WHAT DATA CAN BE PLOTTED Evalplot

------------------------ Evalplot

THIS CODE CAN PLOT VIRTUALLY ANY NEUTRON OR PHOTON CROSS SECTIONS Evalplot

(MF=3 OR 23) AND ANY TABULATED ANGULAR OR ENERGY DISTRIBUTIONS OR Evalplot

LEGENDRE COEFFICIENTS. WHAT IS ACTUALLY PLOTTED DEPENDS ON WHAT Evalplot

DATA IS SELECTED BY THE USER. Evalplot

Evalplot

SELECTION OF DATA Evalplot

----------------- Evalplot

DATA TO BE PLOTTED IS SPECIFIED BY INPUTTING UP TO 100 MAT/MF/MT Evalplot

RANGES OR UP TO 100 ZA/MF/MT RANGES. IN ADDITION FOR EACH RANGE Evalplot

THE USER MAY SPECIFY AN X RANGE (USUALLY ENERGY) AND THE TYPE OF Evalplot

DATA TO BE PLOTTED (SEE: THE DESCRIPTION OF TYPES, BELOW). Evalplot

Evalplot

THE X RANGE FOR MF = 1, 3, 23 AND 27 AND MF = 4 LEGENDRE Evalplot

COEFFICIENTS WILL BE USED AS THE X LIMITS OF THE PLOTS, E.G., Evalplot

PLOT ENERGY DEPENDENT CROSS SECTIONS BETWEEN 1 AND 20 MEV. Evalplot

Evalplot

THE X RANGE FOR MF = 4 AND 5 WILL BE USED TO ONLY SELECT ANGULAR Evalplot

AND ENERGY DISTRIBUTION FOR WHICH THE INCIDENT NEUTRON ENERGY Evalplot

IS IN THE X RANGE. E.G., ONLY PLOT ANGULAR DISTRIBUTIONS WHERE Evalplot

THE INCIDENT NEUTRON ENERGY IS 1 TO 20 MEV. Evalplot

Evalplot

INTERACTIVE VS. BATCH MODE Evalplot

-------------------------- Evalplot

VERSION 92-1 AND LATER VERSIONS OF THIS CODE ONLY USE A BATCH Evalplot

MODE WHERE ALL REQUESTS ARE READ AND PROCESSED. EARLIER VERSIONS Evalplot

OF THIS CODE HAD BOTH AN INTERACTIVE MODE (WHERE REQUESTS WHERE Evalplot

READ AND EXECUTED ONE AT A TIME) AND A BATCH MODE. INTERACTIVE Evalplot

MODE HAS BEEN DROPPED AND WILL NOT TO REINTRODUCED UNLESS THE Evalplot

AUTHOR IS INFORMED BY USERS THAT THEY WERE USING THE INTERACTIVE Evalplot

MODE. Evalplot

Evalplot

PLOT LAYOUT Evalplot

----------- Evalplot

VERSION 92-1 AND LATER VERSIONS OF THIS CODE WILL PLOT ALL Evalplot

CURVES ON A SINGLE PLOT. EARLIER VERSIONS OF THIS CODE ALLOWED Evalplot

THE OPTION TO HAVE, Evalplot

MULTIPLE PLOTS - INDIVIDUAL SCALING Evalplot

MULTIPLE PLOTS - COMMON SCALING Evalplot

SINGLE PLOT Evalplot

MULTILE PLOTS PER PLOT HAVE BEEN DROPPED AND WILL NOT BE Evalplot

REINTRODUCED UNLESS IT IS DEMONSTRATED TO THE AUTHOR THAT THEY Evalplot

ARE OF PRACTICAL USE IN SOME APPLICATION. Evalplot

Evalplot

PROCESSING OF DATA Evalplot

------------------ Evalplot

IN THE CASE OF NEUTRON AND PHOTON CROSS SECTIONS (MF=3 OR 23) Evalplot

AND PARAMETERS (MF=1 OR 27) ALL DATA IN A FILE (MF) IS READ Evalplot

GROUPED TOGETHER BY TYPE (AS EXPLAINED BELOW) AND PLOTTED. Evalplot

Evalplot

IN THE CASE OF ANGULAR AND ENERGY DISTRIBUTIONS (MF=4 OR 5) ONLY Evalplot

ONE SECTION OF DATA AT A TIME IS READ AND PLOTTED. Evalplot

Evalplot

TYPES OF DATA (MF=1, 3, 23 AND 27 ONLY) Evalplot

--------------------------------------- Evalplot

THESE DATA ARE DIVIDED INTO UP TO 18 TYPES AND EACH TYPE OF Evalplot

DATA IS GROUPED TOGETHER AND PLOTTED (IF THE DATA IS ACTUALLY Evalplot

PRESENT). Evalplot

Evalplot

WHAT TYPE OF DATA IS ACTUALLY PLOTTED CAN BE CONTROLLED BY USER Evalplot

INPUT EITHER BASED ON SELECTED MAT/MF/MT OR ZA/MF/MT RANGES OR Evalplot

BY EXPLICITLY SELECTING ONLY ONE TYPE OF DATA IS TO BE PLOTTED Evalplot

(SEE THE DESCRIPTION OF INPUT BELOW). Evalplot

Evalplot

SIMPLE REQUESTS Evalplot

--------------- Evalplot

GENERALLY EACH MAT/MF/MT OR ZA/MF/MT REQUESTED IS TREATED Evalplot

SEPERATELY AND THE SPECIFIED DATA IS GROUPED BY TYPE AND PLOTTED. Evalplot

FOR EXAMPLE, THE USER MAY SPECIFY USING ONE REQUEST THAT ALL Evalplot

TYPES OF DATA BE PLOTTED OVER THE ENTIRE ENERGY RANGE AND USE Evalplot

A SECOND REQUEST TO SPECIFY THAT ONE PARTICULAR TYPE OF DATA Evalplot

BE PLOTTED OVER A SPECIFIC ENERGY RANGE. Evalplot

Evalplot

CHAINED REQUESTS Evalplot

---------------- Evalplot

REQUESTS MAY ALSO BE CHAINED TOGETHER (SEE, THE DESCRIPTION OF Evalplot

INPUT BELOW), WHERE A NUMBER OF REQUESTS MAY BE USED TO SELECT Evalplot

DATA, BUT ONLY THE LAST REQUEST IN A CHAIN WILL CAUSE ALL SELECTED Evalplot

DATA TO BE PLOTTED. CHAINED REQUESTED ARE INDICATED ON INPUT BY Evalplot

A SERIES OF REQUESTS FOR DATA TYPE = -1, EXCEPT FOR THE LAST Evalplot

REQUEST OF THE CHAIN, WHICH MUST SPECIFY A TYPE DATA = 0 (ALL) Evalplot

OR A POSITIVE NUMBER. UNLIKE SIMPLE REQUESTS, WHERE EACH WILL Evalplot

PRODUCE ONE OR MORE PLOTS, WITH CHAINED REQUESTS THE ENTIRE Evalplot

SERIES OF CHAINED REQUESTS WILL BE TREATED AS A SINGLE REQUEST Evalplot

AND WILL PRODUCE ONE OR MORE PLOTS. Evalplot

Evalplot

FOR EXAMPLE, DATA TYPE = 1 WILL NORMALLY INCLUDE, Evalplot

MT = 1 - TOTAL Evalplot

= 2 - ELASTIC Evalplot

= 4 - TOTAL INELASTIC Evalplot

= 18 - FISSION Evalplot

= 102 - CAPTURE Evalplot

IF YOU WISH TO EXCLUDE TOTAL INELASTIC FROM A PLOT YOU NEED ONLY Evalplot

SPECIFY TWO CHAINED REQUESTS THE FIRST TO SELECT MT = 1 THROUGH Evalplot

2 (TO INCLUDE TOTAL AND ELASTIC) AND A SECOND TO INCLUDE MT = 18 Evalplot

THROUGH 102. THE FIRST REQUEST SHOULD SPECIFY DATA TYPE = -1 AND Evalplot

SECOND 1 (THIS WILL CHAIN THE 2 REQUESTS TOGETHER, SO THAT MT =1 Evalplot

THROUGH 2, AND MT = 18 THROUGH 102 ALL APPEAR ON THE SAME PLOT). Evalplot

SINCE MT = 4 (TOTAL INELASTIC) IS NOT REQUESTED IT WILL NOT BE Evalplot

PLOTTED. Evalplot

Evalplot

DEFINITION OF 18 DATA TYPES Evalplot

------------------------------------------------------------------ Evalplot

NEUTRONS (MF = 3) Evalplot

----------------- Evalplot

(1) TOTAL, ELASTIC, CAPTURE, FISSION AND TOTAL INELASTIC Evalplot

(2) (N,2N), (N,3N) AND (N,N' CHARGED PARTICLE) Evalplot

(3) (N,CHARGED PARTICLE) Evalplot

(4) PARTICLE PRODUCTION (PROTON, DEUTERON, ETC.) AND DAMAGE Evalplot

(5) TOTAL, FIRST, SECOND, ETC. CHANCE FISSION. Evalplot

(6) TOTAL INELASTIC, INELASTIC DISCRETE LEVELS AND CONTINUUM Evalplot

(7) (N,P) TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN) Evalplot

(8) (N,D) TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN) Evalplot

(9) (N,T) TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN) Evalplot

(10) (N,HE-3) TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN) Evalplot

(11) (N,ALPHA) TOTAL AND LEVELS (ONLY IF LEVELS ARE GIVEN) Evalplot

(12) PARAMETERS MU-BAR, XI AND GAMMA Evalplot

(13) NU-BAR - TOTAL, PROMPT AND DELAYED Evalplot

Evalplot

PHOTONS (MF=23 AND 27) Evalplot

----------------------- Evalplot

(14) TOTAL, COHERENT, INCOHERENT, TOTAL PHOTOELECTRIC, TOTAL Evalplot

PAIR PRODUCTION Evalplot

(15) TOTAL AND SUBSHELL PHOTOELECTRIC Evalplot

(16) TOTAL, NUCLEAR AND ELECTRON PAIR PRODUCTION Evalplot

(17) COHERENT FORM FACTOR AND INCOHERENT SCATTERING FUNCTION Evalplot

(18) REAL AND IMAGINARY SCATTERING FACTORS Evalplot

Evalplot

IDENTIFICATION OF DATA Evalplot

---------------------- Evalplot

ALL PLOTS IDENTIFY THE TARGET, E.G., U-238 AND UNITS OF THE X AND Evalplot

Y AXIS, E.G., X = ENERGY (MEV) OR COSINE (LAB), ETC., Y = CROSS Evalplot

SECTION (BARNS) OR PROBABILITY/COSINE, ETC. Evalplot

Evalplot

FOR TYPES OF DATA (MF=1, 3, 23 AND 27) DIFFERENT REACTIONS (MT) Evalplot

ARE GROUPED TOGETHER TO APPEAR ON THE SAME PLOT. THE TITLE AT Evalplot

THE TOP OF THE PLOT WILL IDENTIFY THE TYPE OF DATA BEING PLOTTED Evalplot

AND THE LEGEND BOX WITHIN THE PLOT WILL IDENTIFY EACH REACTION. Evalplot

Evalplot

FOR ANGULAR AND ENERGY DISTRIBUTIONS (MF=4 OR 5) EACH PLOT WILL Evalplot

CONTAIN DATA FOR A SINGLE REACTION (MT) AND DIFFERENT INCIDENT Evalplot

NEUTRON ENERGIES. THE TITLE AT THE TOP OF THE PLOT WILL IDENTIFY Evalplot

THE REACTION AND THE LEGEND BOX WITHIN THE PLOT WILL IDENTIFY Evalplot

THE INCIDENT ENERGY. Evalplot

Evalplot

FOR LEGENDRE COEFFICIENT THE DATA IN ENDF/B FORMAT WILL BE Evalplot

INVERTED IN ORDER TO PRESENT EACH LEGENDRE COEFFICIENT VERSUS Evalplot

INCIDENT ENERGY. THE TITLE AT THE TOP OF THE PLOT WILL IDENTIFY Evalplot

THE REACTION AND THE LEGEND BOX WITHIN THE PLOT WILL IDENTIFY Evalplot

THE LEGENDRE ORDER. Evalplot

Evalplot

INPUT FILES Evalplot

----------- Evalplot

UNIT DESCRIPTION Evalplot

---- ----------- Evalplot

2 INPUT LINES (BCD - 80 CHARACTERS/RECORD) Evalplot

9 MT DEFINITIONS (BCD - 80 CHARACTERS/RECORD) Evalplot

10 ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Evalplot

12 SOFTWARE CHARACTERS (BCD - 80 CHARACTERS/RECORD) Evalplot

Evalplot

OUTPUT FILES Evalplot

------------ Evalplot

UNIT DESCRIPTION Evalplot

---- ----------- Evalplot

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Evalplot

16 PLOTTING UNIT Evalplot

Evalplot

SCRATCH FILES Evalplot

------------- Evalplot

UNIT DESCRIPTION Evalplot

---- ----------- Evalplot

11 SCRATCH FILE (BINARY - 960000 WORDS/RECORD = 2*PAGE SIZE) Evalplot

Evalplot

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Evalplot

--------------------------------------------------------------- Evalplot

UNIT FILE NAME Evalplot

---- ---------- Evalplot

2 EVALPLOT.INP Evalplot

3 EVALPLOT.LST Evalplot

9 MT.DAT Evalplot

10 ENDFB.IN (OR AS INPUT PARAMETER) Evalplot

11 (SCRATCH) Evalplot

12 PLOT.CHR Evalplot

16 (PLOTTING UNIT...USUALLY A DUMMY) Evalplot

Evalplot

INPUT PARAMETERS Evalplot

---------------- Evalplot

LINE COLUMNS FORMAT DESCRIPTION Evalplot

---- ------- ------ ----------- Evalplot

1 1-11 E11.4 LOWER X LIMIT OF PLOTTER Evalplot

12-22 E11.4 UPPER X LIMIT OF PLOTTER Evalplot

23-33 E11.4 LOWER Y LIMIT OF PLOTTER Evalplot

34-44 E11.4 UPPER Y LIMIT OF PLOTTER Evalplot

45-55 I11 NUMBER OF PLOTS PER FRAME IN X DIRECTION Evalplot

56-66 I11 NUMBER OF PLOTS PER FRAME IN Y DIRECTION Evalplot

67-70 F4.1 CHARACTER SIZE MULTIPLIER Evalplot

= 0 OR 1 - NORMAL CHARACTER SIZE Evalplot

= OTHERWISE - CHARACTERS SCALED BY THIS Evalplot

FACTOR. Evalplot

2 1-60 A60 ENDF/B DATA FILENAME Evalplot

(LEAVE BLANK FOR STANDARD = ENDFB.IN) Evalplot

3 1-11 I11 RETRIEVAL CRITERIA Evalplot

= 0 - MAT Evalplot

= 1 - ZA Evalplot

12-22 I11 TYPE OF GRID Evalplot

= 0 - TICK MARKS ON BORDER Evalplot

= 1 - SOLID AT COARSE INTERVALS Evalplot

= 2 - DASHED AT COARSE INTERVALS Evalplot

= 3 - SOLID AT FINE INTERVALS Evalplot

= 4 - DASHED AT FINE INTERVALS Evalplot

= 5 - SOLID COARSE/DASHED FINE GRID Evalplot

23-33 I11 SHOULD BORDER BE PLOTTED ON EACH PLOT Evalplot

= 0 - NO Evalplot

= 1 - YES Evalplot

34-44 I11 LINE THICKNESS Evalplot

= 0 - 5 = BORDER/CURVES/CHARACTERS Evalplot

=-1 - -5 = BORDER/CURVES (NOT CHARACTERS) Evalplot

NOTE, THE GRID IS NEVER THICK. Evalplot

45-55 I11 SHOULD TEMPERATURE BE PLOTTED. Evalplot

= 0 - YES Evalplot

= 1 - NO Evalplot

56-66 E11.4 ALLOWABLE RATIO OF PLOT Y RANGE MAXIMUM TO Evalplot

MINIMUM - IF THIS RATIO IS EXCEEDED THE Y Evalplot

RANGE MINIMUM WILL BE CHANGED TO THE Y RANGE Evalplot

MAXIMUM TIMES THIS RATIO. Evalplot

IF THIS RATIO IS NOT POSITIVE, IT IS Evalplot

INTERPRETED TO MEAN NO LIMIT ON Y RANGE. Evalplot

67-70 I4 BACKGROUND COLOR Evalplot

= 0 = BLACK Evalplot

= OTHERWISE = WHITE Evalplot

4-N 1- 6 I6 LOWER MAT OR ZA LIMIT Evalplot

7- 8 I2 LOWER MF LIMIT Evalplot

9-11 I3 LOWER MT LIMIT Evalplot

11-22 E11.4 LOWER X LIMIT (USUALLY ENERGY) - EV Evalplot

23-28 I6 UPPER MAT OR ZA LIMIT Evalplot

29-30 I2 UPPER MF LIMIT Evalplot

31-33 I3 UPPER MT LIMIT Evalplot

34-44 E11.4 UPPER X LIMIT (USUALLY ENERGY) - EV Evalplot

45-55 I11 TYPE OF DATA TO RETRIEVE AND PLOT Evalplot

= -1 - CHAIN THIS REQUEST TO THE NEXT ONE Evalplot

= 0 - ALL Evalplot

= 1-18 - TYPE AS SPECIFIED ABOVE Evalplot

Evalplot

THERE MAY BE UP 100 MAT/MF/MT OR ZA/MF/MT REQUEST RANGES. INPUT Evalplot

MUST BE TERMINATED BY A BLANK LINE. Evalplot

Evalplot

IF X LIMITS ARE NOT SPECIFIED (I.E., LOWER AND UPPER X LIMIT = 0) Evalplot

THIS WILL BE INTERPRETED TO MEAN NO LIMIT AND ALL DATA WILL BE Evalplot

PLOTTED OVER THEIR ENTIRE ENERGY RANGE, I.E., YOU NEED NOT Evalplot

KNOW AND SPECIFY THE ACTUAL ENERGY LIMITS OF THE DATA. Evalplot

Evalplot

EXAMPLE DEFINITION OF PLOTTER Evalplot

----------------------------- Evalplot

THE FIRST INPUT LINE DEFINES THE DIMENSIONS OF THE PLOTTER BEING Evalplot

USED IN ANY UNITS (INCHES, CENTIMETERS, MILLIMETERS, ANYTHING) Evalplot

WHICH APPLY TO THE PLOTTER. IN ADDITION THE FIRST LINE DEFINES Evalplot

HOW MANY PLOTS SHOULD APPEAR ON EACH FRAME. THE PLOTTING AREA Evalplot

DEFINED ON THE FIRST INPUT LINE MAY BE SUBDIVIDED INTO ANY NUMBER Evalplot

OF PLOTS IN THE X AND Y DIRECTION. FOR EXAMPLE, TO PRODUCE A Evalplot

SERIES OF FRAMES EACH CONTAINING 3 PLOTS IN THE X DIRECTION AND Evalplot

2 PLOTS IN THE Y DIRECTION (6 PLOTS PER FRAME) COLUMN 45-55 OF Evalplot

THE FIRST INPUT LINE SHOULD BE 3 AND COLUMNS 56-66 SHOULD BE 2. Evalplot

Evalplot

IF THE LOCAL PLOTTER USES DIMENSIONS OF INCHES IN ORDER TO OBTAIN Evalplot

10 X 10 INCH FRAMES WITH 3 X 2 PLOTS PER FRAME THE FIRST INPUT Evalplot

LINE SHOULD BE, Evalplot

Evalplot

0.0 10.0 0.0 10.0 3 2 Evalplot

Evalplot

IF THE LOCAL PLOTTER USES DIMENSION OF MILLIMETERS THE SAME Evalplot

PHYSICAL SIZE PLOT MAY BE OBTAINED IF THE FIRST INPUT LINE IS, Evalplot

Evalplot

0.0 254.0 0.0 254.0 3 2 Evalplot

Evalplot

FOR SIMPLICITY THE FOLLOWING EXAMPLE INPUTS WILL NOT DISCUSS THE Evalplot

PHYSICAL DIMENSIONS OF THE PLOTTER AND THE FIRST INPUT LINE WILL Evalplot

IN ALL CASES INDICATE 10 X 10 INCH PLOTS WITH ONLY 1 PLOT PER Evalplot

FRAME. Evalplot

Evalplot

ALL OF THE FOLLOWING EXAMPLE WILL USE, Evalplot

1) A DASHED GRID (SECOND LINE, COLS. 12-22 = 2) Evalplot

2) NO BORDER (SECOND LINE, COLS. 23-33 = 0) Evalplot

3) LINE THICKNESS -2 (SECOND LINE, COLS. 34-44 =-2) Evalplot

4) TEMPERATURE ON PLOTS (SECOND LINE, COLS. 45-55 = 0) Evalplot

5) NO Y RANGE LIMIT (SECOND LINE, COLS. 56-66 = 0.0) Evalplot

Evalplot

EXAMPLE INPUT NO. 1 Evalplot

------------------- Evalplot

FOR ALL THORIUM AND URANIUM ISOTOPES PLOT NEUTRON CROSS SECTIONS Evalplot

ENTIRE ENERGY RANGE. IN ADDITION PLOT TYPE 1 DATA, MAJOR NEUTRON Evalplot

CROSS SECTIONS OVER THE ENERGY RANGE 1 EV TO 1 KEV. USE THE Evalplot

STANDARD FILENAME (ENDFB.IN) FOR THE ENDF/B DATA. THE FOLLOWING Evalplot

6 INPUT LINES ARE REQUIRED, Evalplot

Evalplot

0.0 10.0 0.0 10.0 3 2 Evalplot

ENDFB.IN Evalplot

1 2 0 -2 0 0.0 Evalplot

90000 3 0 90999 3999 0 Evalplot

90000 3 0 1.00000+ 090999 3999 1.00000+ 3 1 Evalplot

(BLANK LINE MUSE FOLLOW LAST REQUEST) Evalplot

Evalplot

EXAMPLE INPUT NO. 2 Evalplot

------------------- Evalplot

PLOT FE-56 ELASTIC AND INELASTIC ANGULAR DISTRIBUTIONS BETWEEN Evalplot

1 AND 20 MEV. THE FOLLOWING 6 INPUT LINES ARE REQUIRED, Evalplot

Evalplot

0.0 10.0 0.0 10.0 3 2 Evalplot

ENDFB.IN Evalplot

1 2 0 -2 0 0.0 Evalplot

26056 4 2 1.00000+ 626056 4 2 2.00000+ 7 0 Evalplot

26056 4 4 1.00000+ 626056 4 4 2.00000+ 7 0 Evalplot

(BLANK LINE MUSE FOLLOW LAST REQUEST) Evalplot

Evalplot

EXAMPLE INPUT NO. 3 (CHAINED INPUT) Evalplot

----------------------------------- Evalplot

FOR ALL THORIUM AND URANIUM ISOTOPES PLOT TOTAL, ELASTIC ,CAPTURE Evalplot

AND FISSION, BUT NOT INELASTIC CROSS SECTIONS OVER THERE ENTIRE Evalplot

ENERGY RANGE AND FROM 1 KEV TO 1 MEV. THE FOLLOWING 8 INPUT Evalplot

LINES ARE REQUIRED, Evalplot

Evalplot

0.0 10.0 0.0 10.0 3 2 Evalplot

ENDFB.IN Evalplot

1 2 0 -2 0 0.0 Evalplot

90000 3 1 90999 3 2 -1 Evalplot

90000 3 18 90999 3102 1 Evalplot

90000 3 1 1.00000+ 390999 3 2 1.00000+ 6 -1 Evalplot

90000 3 18 1.00000+ 390999 3102 1.00000+ 6 1 Evalplot

(BLANK LINE MUSE FOLLOW LAST REQUEST) Evalplot

Evalplot

NOTE, THIS EXAMPLE INCLUDES 2 CHAINED REQUESTED - INPUT LINES 3 Evalplot

AND 4 SELECTING DATA AND PRODUCING A PLOT OVER THE ENTIRE ENERGY Evalplot

RANGE AND INPUT LINES 5 AND 6 SELECTING THE SAME DATA AND Evalplot

PRODUCING A PLOT FROM 1 KEV TO 1 MEV. Evalplot

Evalplot

ANY NUMBER OF REQUEST LINES MAY TO CHAINED TOGETHER TO SELECT Evalplot

DATA. THE CHAIN ENDS WHERE THE TYPE OF DATA (COLS. 45-55) IS NOT Evalplot

NEGATIVE AND THEN THE SELECTED DATA WILL BE PLOTTED. Evalplot

Evalplot

EXAMPLE INPUT NO. 4 Evalplot

------------------- Evalplot

FOR THE SAME EXAMPLE AS ABOVE, EXCEPT USE A DIFFERENT FILENAME Evalplot

FOR THE ENDF/B DATA TO READ FROM A FILE TREE STRUCTURE. THE Evalplot

FOLLOWING 8 INPUT LINES ARE REQUIRED, Evalplot

Evalplot

0.0 10.0 0.0 10.0 3 2 Evalplot

EVALUATION/ENDFB6/THORIUM Evalplot

1 2 0 -2 0 0.0 Evalplot

90000 3 1 90999 3 2 -1 Evalplot

90000 3 18 90999 3102 1 Evalplot

90000 3 1 1.00000+ 390999 3 2 1.00000+ 6 -1 Evalplot

90000 3 18 1.00000+ 390999 3102 1.00000+ 6 1 Evalplot

(BLANK LINE MUST FOLLOW LAST REQUEST) Evalplot

Evalplot

===== PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Evalplot

Evalplot

THIS PROGRAM USES A SIMPLE CALCOMP LIKE INTERFACE INVOLVING Evalplot

ONLY 6 SUBROUTINES, Evalplot

Evalplot

STARPLOT - INITIALIZE PLOTTER Evalplot

NEXTPLOT - CLEAR THE SCREEN FOR THE NEXT PLOT Evalplot

ENDPLOTS - TERMINATE PLOTTING Evalplot

Evalplot

PLOT(X,Y,IPEN) - DRAW OR MOVE FROM LAST LOCATION TO (X,Y), Evalplot

END OF CURRENT PLOT OR END OF PLOTTING. Evalplot

IPEN = 2 - DRAW Evalplot

= 3 - MOVE Evalplot

Evalplot

PEN(IPEN) - SELECT COLOR. Evalplot

IPEN- COLOR = 1 TO N (N = ANY POSITIVE INTEGER) Evalplot

Evalplot

BOXCOLOR(X,Y,IFILL,IBORDER) - FILL A RECTANGULAR BOX DEFINED Evalplot

BY THE X AND Y CORNERS - X(1), Evalplot

X(2), Y(1),Y(2) Evalplot

IFILL - COLOR TO FILL BOX WITH Evalplot

IBORDER - COLOR OF BOX BORDER Evalplot

Evalplot

IN ORDER TO INTERFACE THIS PROGRAM FOR USE ON ANY PLOTTER WHICH Evalplot

DOES NOT USE THE ABOVE CONVENTIONS IT IS MERELY NECESSARY FOR THE Evalplot

THE USER TO WRITE 6 SUBROUTINES WITH THE NAMES PLOTS, PLOT AND PEN Evalplot

WITH THE SUBROUTINE ARGUMENTS DESCRIBED ABOVE AND TO THEN CALL THE Evalplot

LOCAL EQUIVALENT ROUTINES. Evalplot

Evalplot

COLOR PLOTS Evalplot

------------------------------------------------------------------ Evalplot

TO SELECT PLOTTING COLORS SUBROUTINE PEN (DESCRIBED ABOVE) IS USED Evalplot

TO SELECT ONE OF THE AVAILABLE COLORS. IF YOU HAVE COLOR ON YOUR Evalplot

PLOTTER YOU SHOULD PROVIDE A SUBROUTINE PEN TO SELECT COLORS. Evalplot

Evalplot

BLACK AND WHITE PLOTS Evalplot

------------------------------------------------------------------ Evalplot

WHEN PRODUCING BLACK AND WHITE PLOTS SUBROUTINE PEN NEED MERELY Evalplot

BE A DUMMY SUBROUTINE TO IGNORE ANY ATTEMPT TO CHANGE COLORS, Evalplot

Evalplot

SUBROUTINE PEN(IPEN) Evalplot

RETURN Evalplot

END Evalplot

Evalplot

SIMILAR BOXCOLOR CAN BE A DUMMY Evalplot

Evalplot

SUBROUTINE BOXCOLOR(X,Y,IFILL,IBORDER) Evalplot

RETURN Evalplot

END Evalplot

Evalplot

CHARACTER SET Evalplot

------------------------------------------------------------------ Evalplot

THIS PROGRAM USES COMPUTER AND PLOTTER DEVICE INDEPENDENT SOFTWARE Evalplot

CHARACTERS. THIS PROGRAM COMES WITH A FILE THAT DEFINES THE PEN Evalplot

STROKES REQUIRED TO DRAW ALL CHARACTERS ON AN IBM KEYBOARD (UPPER Evalplot

AND LOWER CASE CHARACTERS, NUMBERS, ETC.) PLUS AN ALTERNATE SET OF Evalplot

ALL UPPER AND LOWER CASE GREEK CHARACTERS AND ADDITIONAL SPECIAL Evalplot

SYMBOLS. Evalplot

Evalplot

THE SOFTWARE CHARACTER TABLE CONTAINS X AND Y AND PEN POSITIONS TO Evalplot

DRAW EACH CHARACTER. IF YOU WISH TO DRAW ANY ADDITIONAL CHARACTERS Evalplot

OR TO MODIFY THE FONT OF THE EXISTING CHARACTERS YOU NEED ONLY Evalplot

MODIFY THIS TABLE. Evalplot

Evalplot

ADDITIONAL FONTS Evalplot

---------------- Evalplot

THIS PROGRAM COMES WITH 3 COMPLETE SETS OF THE SAME CHARACTERS Evalplot

USING DIFFERENT FONTS. FOR SPEED IN PLOTTING IT IS RECOMMENDED Evalplot

THAT YOU USE THE SIMPLEX FONT. FOR FINISHED PLOTS SUITABLE FOR Evalplot

PUBLICATION, BUT REQUIRING MORE TIME TO GENERATE A PLOT, IT IS Evalplot

RECOMMENDED THAT YOU USE THE DUPLEX OR COMPLEX FONT - YOU CAN Evalplot

EXPERIMENT WITH ANY OF THE 3 FONTS TO DETERMINE WHICH BEST MEETS Evalplot

YOUR NEEDS. Evalplot

Evalplot

TO USE ANY ONE OF THE FONTS MERELY BY SURE THAT IT IS DEFINED AS Evalplot

UNIT 12 FOR INPUT (IF USING STANDARD FILENAMES IT SHOULD BE Evalplot

NAMED PLOT.CHR). SO THAT SWITCHING FONTS CAN BE SIMPLY DONE Evalplot

MERELY BY COPYING THE FONT THAT YOU WANT TO THE UNIT 12 THAT Evalplot

YOU ARE USING FOR INPUT. Evalplot

Evalplot

CONTROL CHARACTERS Evalplot

------------------------------------------------------------------ Evalplot

IN THE SOFTWARE CHARACTER TABLE ALL CHARACTERS TO BE PLOTTED WILL Evalplot

HAVE PEN POSITION = 2 (DRAW) OR = 3 (MOVE). IN ADDITION THE TABLE Evalplot

CURRENTLY CONTAINS 4 CONTROL CHARACTERS, Evalplot

Evalplot

PEN POSITION = 0 Evalplot

---------------- Evalplot

SHIFT THE NEXT PRINTED CHARACTER BY X AND Y. 3 CONTROL CHARACTERS Evalplot

ARE PRESENTLY INCLUDED IN THE SOFTWARE CHARACTER TABLE TO ALLOW Evalplot

SHIFTING. Evalplot

Evalplot

{ = SHIFT UP (FOR SUPERSCRIPTS..............X= 0.0, Y= 0.5) Evalplot

} = SHIFT DOWN (FOR SUBSCRIPTS..............X= 0.0, Y=-0.5) Evalplot

\ = SHIFT LEFT 1 CHARACTER (FOR BACKSPACE...X=-1.0, Y= 0.0) Evalplot

Evalplot

PEN POSITION =-1 Evalplot

---------------- Evalplot

SELECT THE NEXT PRINTED CHARACTER FROM THE ALTERNATE CHARACTER Evalplot

SET. AT PRESENT THIS CONTROL CHARACTER IS, Evalplot

Evalplot

| = SWITCH TO ALTERNATE CHARACTER SET Evalplot

Evalplot

THESE 4 CONTROL CHARACTERS ARE ONLY DEFINED BY THE VALUE OF THE Evalplot

PEN POSITION IN THE SOFTWARE CHARACTER TABLE (I.E., THEY ARE NOT Evalplot

HARD WIRED INTO THIS PROGRAM). AS SUCH BY MODIFYING THE SOFTWARE Evalplot

CHARACTER TABLE THE USER HAS THE OPTION OF DEFINING ANY CONTROL Evalplot

CHARACTERS TO MEET SPECIFIC NEEDS. Evalplot

Evalplot

THESE CHARACTERS MAY BE USED IN CHARACTER STRINGS TO PRODUCE Evalplot

SPECIAL EFFECTS. FOR EXAMPLE, TO PLOT SUBSCRIPT 5, B, SUPERSCRIPT Evalplot

10 USE THE STRING, Evalplot

Evalplot

}5B{1{0 Evalplot

Evalplot

TO PLOT B, SUBSCRIPT 5 AND SUPERSCRIPT 10 WITH THE 5 DIRECTLY Evalplot

BELOW THE 1 OF THE 10 WE CAN USE THE BACKSPACE CHARACTER TO Evalplot

POSITION THE 1 DIRECTLY ABOVE THE 5 USING THE STRING, Evalplot

Evalplot

B}5\{1{0 Evalplot

Evalplot

TO PLOT UPPER CASE GREEK GAMMA FOLLOWED BY THE WORD TOTAL (I.E., Evalplot

RESONANCE TOTAL WIDTH) USE THE STRING. Evalplot

Evalplot

|G TOTAL Evalplot

Evalplot

NOTE, WHEN THESE CONTROL CHARACTERS ARE USED THEY ONLY EFFECT THE Evalplot

NEXT 1 PRINTED CHARACTER (SEE, ABOVE EXAMPLE OF PLOTTING SUPER- Evalplot

SCRIPT 10 WHERE THE SHIFT UP CONTROL CHARACTER WAS USED BEFORE THE Evalplot

1 AND THEN AGAIN BEFORE THE 0 AND THE BACKSPACE AND SHIFT UP Evalplot

CONTROL CHARACTERS WERE USED IN COMBINATION). Evalplot

Evalplot

IF THESE 4 CONTROL CHARACTERS ARE NOT AVAILABLE ON YOUR COMPUTER Evalplot

YOU CAN MODIFY THE SOFTWARE CHARACTER TABLE TO USE ANY OTHER 4 Evalplot

CHARACTERS THAT YOU DO NOT NORMALLY USE IN CHARACTER STRINGS (FOR Evalplot

DETAILS SEE THE SOFTWARE CHARACTER TABLE). Evalplot

Evalplot

STANDARD/ALTERNATE CHARACTER SETS Evalplot

------------------------------------------------------------------ Evalplot

THE SOFTWARE CHARACTER TABLE CONTAINS 2 SETS OF CHARACTERS WHICH Evalplot

ARE A STANDARD SET (ALL CHARACTERS ON AN IBM KEYBOARD) AND AN Evalplot

ALTERNATE SET (UPPER AND LOWER CASE GREEK CHARACTERS AND SPECIAL Evalplot

CHARACTERS). TO DRAW A CHARACTER FROM THE ALTERNATE CHARACTER SET Evalplot

PUT A RIGHT BRACKET CHARACTER (|) BEFORE A CHARACTER (SEE THE Evalplot

ABOVE EXAMPLE AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS Evalplot

CONTROL CHARACTER WILL ONLY EFFECT THE NEXT 1 PLOTTED CHARACTER. Evalplot

Evalplot

SUB AND SUPER SCRIPTS Evalplot

------------------------------------------------------------------ Evalplot

TO DRAW SUBSCRIPT PRECEED A CHARACTER BY }. TO DRAW SUPERSCRIPT Evalplot

PRECEED A CHARACTER BY { (SEE THE ABOVE EXAMPLE AND THE SOFTWARE Evalplot

CHARACTER TABLE FOR DETAILS). THESE CONTROL CHARACTER WILL ONLY Evalplot

EFFECT THE NEXT 1 PLOTTED CHARACTER. Evalplot

Evalplot

BACKSPACING Evalplot

------------------------------------------------------------------ Evalplot

TO BACKSPACE ONE CHARACTER PRECEED A CHARACTER BY \ (SEE, THE Evalplot

ABOVE EXAMPLE AND THE SOFTWARE CHARACTER TABLE FOR DETAILS). THIS Evalplot

CONTROL CHARACTER WILL PERFORM A TRUE BACKSPACE AND WILL EFFECT Evalplot

ALL FOLLOWING CHARACTERS IN THE SAME CHARACTER STRING. Evalplot

Evalplot

PLOT DIMENSIONS Evalplot

--------------- Evalplot

ARE DEFINED BY USER INPUT. INTERNALLY THE PROGRAM WILL CREATE A Evalplot

PLOT IN APPROXIMATELY A4 OR 8-1/2 BY 11 INCH FORMAT. DURING Evalplot

OUTPUT THE PLOT IS TRANSFORMED TO THE UNITS (INCHES, CENTIMETERS, Evalplot

MILLIMETERS, WHATEVER) OF THE PLOTTER BEING USED AND OUTPUT. Evalplot

Evalplot

===== PLOTTER/GRAPHICS TERMINAL INTERFACE ============================= Evalplot

======================================================================= Evalplot

======================================================================= Fixup

Fixup

PROGRAM FIXUP Fixup

VERSION 84-1 (NOVEMBER 1984) Fixup

VERSION 86-1 (JANUARY 1986) *IMPROVED BASED ON USER COMMENTS Fixup

*FORTRAN-77/H VERSION Fixup

VERSION 86-2 (JUNE 1986) *ALLOW CREATION OF SECTIONS OF CROSS Fixup

SECTIONS WHICH ARE NOT PRESENT IN Fixup

THE ORIGINAL EVALUATION Fixup

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Fixup

FILE NAMES (SEE, SUBROUTINE FILEIO Fixup

FOR DETAILS). Fixup

*IMPROVED BASED ON USER COMMENTS. Fixup

VERSION 89-1 (JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO Fixup

INSURE PROGRAM WILL NOT DO ANYTHING Fixup

CRAZY. Fixup

*UPDATED TO USE NEW PROGRAM CONVERT Fixup

KEYWORDS. Fixup

*ADDED LIVERMORE CIVIC COMPILER Fixup

CONVENTIONS. Fixup

VERSION 89-2 (MARCH 1989) *ADDED ENDF/B-VI SUMMATION RULES AND Fixup

DEFINED MF AND MT NUMBERS. PROGRAM Fixup

WILL NOW USE MF=1, MT=451 TO DEFINE Fixup

THE ENDF/B FORMAT OF THE DATA (E.G., Fixup

ENDF/B-VI OR EARLIER) AND USE THE Fixup

CORRECT SUMMATION RULES FOR EACH Fixup

VERSION OF THE ENDF/B FORMAT. IF Fixup

MF=1, MT=451 IS NOT PRESENT PROGRAM Fixup

WILL USE ENDF/B-VI SUMMATION Fixup

CONVENTIONS AS A DEFAULT. Fixup

VERSION 90-1 (JUNE 1990) *UPDATED BASED ON USER COMMENTS Fixup

*ADDED PHOTON INTERACTION, MF=23 Fixup

VERSION 91-1 (JUNE 1991) *ADDED FORTRAN SAVE OPTION Fixup

*NEW MORE CONSISTENT ENERGY OUTPUT Fixup

ROUTINE Fixup

VERSION 92-1 (JANUARY 1992) *ADDED OPTION TO CALCULATE RATIOS, Fixup

E.G., CAPTURE/FISSION AND PRODUCTS, Fixup

NU-BAR*FISSION - AND OUTPUT THE Fixup

RESULTS IN THE ENDF/B FORMAT (SEE, Fixup

BELOW - CREATING RATIOS AND PRODUCTS) Fixup

*ALLOW TOTAL NU-BAR (MF=1, MT=452) TO Fixup

BE USED IN DEFINING RATIOS OR Fixup

PRODUCTS. Fixup

*ALLOW ALL CROSS SECTIONS TO BE PUT Fixup

ON A UNIFORM ENERGY GRID. Fixup

*NOTE, CHANGE IN INPUT FORMAT FOR Fixup

RANGES OF MT NUMBERS Fixup

*COMPLETELY CONSISTENT I/O ROUTINES - Fixup

TO MINIMIZE COMPUTER DEPENDENCE. Fixup

VERSION 93-1 (JULY 1993) *CORRECTED ALGORITHM TO CREATE UNIFORM Fixup

ENERGY GRID. Fixup

VERSION 94-1 (JANUARY 1993) *VARIABLE ENDF/B DATA FILENAMES Fixup

TO ALLOW ACCESS TO FILE STRUCTURES Fixup

(WARNING - INPUT PARAMETER FORMAT Fixup

HAS BEEN CHANGED) Fixup

*INCREASED PAGE SIZE FROM 1002 TO Fixup

12000 DATA POINTS. Fixup

*CLOSE ALL FILES BEFORE TERMINATING Fixup

(SEE, SUBROUTINE ENDIT) Fixup

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Fixup

*IMPROVED COMPUTER INDEPENDENCE Fixup

*ALL DOUBLE PRECISION Fixup

*ON SCREEN OUTPUT Fixup

*UNIFORM TREATMENT OF ENDF/B I/O Fixup

*IMPROVED OUTPUT PRECISION Fixup

*DEFINED SCRATCH FILE NAMES Fixup

*INCREASED PAGE SIZE FROM 12000 TO Fixup

36000 DATA POINTS. Fixup

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Fixup

POINT READ FOR MORE DIGITS Fixup

*UPDATED TEST FOR ENDF/B FORMAT Fixup

VERSION BASED ON RECENT FORMAT CHANGE Fixup

*GENERAL IMPROVEMENTS BASED ON Fixup

USER FEEDBACK Fixup

VERSION 99-2 (JUNE 1999) *ASSUME ENDF/B-VI, NOT V, IF MISSING Fixup

MF=1, MT-451. Fixup

*FIXED CREATION OF SECTIONS Fixup

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Fixup

USER FEEDBACK Fixup

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Fixup

*SUMMATION RULES ARE DEFINED BASED Fixup

ON CONTENTS OF TABLES. Fixup

VERS. 2004-1 (JAN. 2004) *GENERAL UPDATE BASED ON USER FEEDBACK Fixup

*INCREASED PAGE SIZE FROM 36000 TO Fixup

60000 DATA POINTS. Fixup

Fixup

OWNED, MAINTAINED AND DISTRIBUTED BY Fixup

------------------------------------ Fixup

THE NUCLEAR DATA SECTION Fixup

INTERNATIONAL ATOMIC ENERGY AGENCY Fixup

P.O. BOX 100 Fixup

A-1400, VIENNA, AUSTRIA Fixup

EUROPE Fixup

Fixup

ORIGINALLY WRITTEN BY Fixup

------------------------------------ Fixup

DERMOTT E. CULLEN Fixup

UNIVERSITY OF CALIFORNIA Fixup

LAWRENCE LIVERMORE NATIONAL LABORATORY Fixup

L-159 Fixup

P.O. BOX 808 Fixup

LIVERMORE, CA 94550 Fixup

U.S.A. Fixup

TELEPHONE 925-423-7359 Fixup

E. MAIL CULLEN1@LLNL.GOV Fixup

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Fixup

Fixup

PURPOSE Fixup

======= Fixup

THIS PROGRAM IS DESIGNED TO READ EVALUATED DATA IN THE ENDF/B Fixup

FORMAT, PERFORM CORRECTIONS AND OUTPUT THE RESULT IN THE ENDF/B Fixup

FORMAT. TWO TYPES OF CORRECTIONS ARE POSSIBLE (1) AUTOMATIC AND Fixup

(2) OPTIONAL (BASED ON USER INPUT) CORRECTIONS. Fixup

Fixup

ONE OF THE MOST IMPORTANT FUNCTIONS OF THIS PROGRAM IS TO Fixup

RE-DEFINE ALL REDUNDANT CROSS SECTIONS (E.G. TOTAL) TO BE EXACTLY Fixup

EQUAL TO THE SUM OF ITS PARTS. THIS PROCEDURE ELIMINATES THE Fixup

PROBLEM WITH MANY ENDF/B EVALUATIONS, WHERE DUE TO THE USE OF Fixup

NON-LINEAR INTERPOLATION LAWS THE TOTAL MAY BE EQUAL TO THE SUM Fixup

OF ITS PARTS AT ALL TABULATED ENERGIES, BUT BASED ON THE Fixup

INTERPOLATION LAWS IT CAN BE QUITE DIFFERENT AT ENERGIES BETWEEN Fixup

TABULATED ENERGIES. Fixup

Fixup

AUTOMATIC CHECKS/CORRECTIONS Fixup

============================ Fixup

(1) CHECK THAT MAT/MF/MT DOES NOT CHANGE UNLESS A MEND/FEND/SEND Fixup

LINE IS READ. IF MAT/MF/MT CHANGES A WARNING MESSAGE IS Fixup

PRINTED BUT NO CORRECTIVE ACTION IS TAKEN. Fixup

(2) ALL LINES WITHIN A GIVEN MAT WILL BE SEQUENTIALLY NUMBERED Fixup

ON OUTPUT. Fixup

Fixup

OPTIONAL CHECKS/CORRECTIONS Fixup

=========================== Fixup

THE FOLLOWING NUMBERS CORRESPOND TO THE INPUT DATA OPTION COLUMNS Fixup

(SEE THE DESCRIPTION OF THE INPUT BELOW) Fixup

Fixup

(1) CORRECT ZA AND AWR IN ALL SECTIONS. CHECK TO INSURE THAT THE Fixup

C1 AND C2 VALUES (ZA AND AWR) ARE THE SAME IN ALL SECTIONS. Fixup

THE C1 AND C2 OF THE FIRST SECTION READ ARE ASSUMED TO BE Fixup

CORRECT AND ARE USED FOR COMPARISON. IF THE C1 AND/OR C2 OF Fixup

THE FIRST SECTION ARE NOT POSITIVE AN ERROR MESSAGE IS OUTPUT Fixup

AND THE MATERIAL IS COPIED WITHOUT CHANGE. Fixup

NOTE....TO CHANGE THE ZA AND/OR AWR OF ANY MATERIAL IT IS Fixup

MERELY NECESSARY TO CHANGE THE ZA AND/OR AWR IN THE FIRST Fixup

SECTION OF THE MATERIAL AND USE THIS OPTION TO AUTOMATICALLY Fixup

CHANGE ALL OTHER SECTIONS. Fixup

(2) CORRECT CROSS SECTION (MF=3) THRESHOLDS. THE Q-VALUE AND AWR Fixup

ARE USED TO DERIVE THE REACTION THRESHOLD USING THE RELATION, Fixup

Fixup

E-THRESHOLD = -(Q-VALUE)*(AWRE+1.0)/AWRE Fixup

Fixup

IF THE THRESHOLD IS POSITIVE THE CROSS SECTION IS CHECKED TO Fixup

INSURE THAT THE FIRST TABULATED POINT IS AT THE THRESHOLD AND Fixup

HAS A ZERO CROSS SECTION. IF NOT, THE CROSS SECTION WILL BE Fixup

CHANGED. Fixup

(A) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND Fixup

HAS A ZERO CROSS SECTION, THE POINT IS DELETED AND A POINT Fixup

IS INSERTED AT THE THRESHOLD. Fixup

(B) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND Fixup

HAS A NON-ZERO CROSS SECTION, A POINT WITH ZERO CROSS Fixup

SECTION IS INSERTED AT THE THRESHOLD. Fixup

(C) IF THE FIRST TABULATED POINT IS BELOW THE THRESHOLD AND Fixup

HAS A NON-ZERO CROSS SECTION, ALL POINTS BELOW THE Fixup

THRESHOLD ARE DELETED AND A POINT WITH ZERO CROSS SECTION Fixup

IS INSERTED AT THE THRESHOLD. Fixup

(3) EXTEND ALL CROSS SECTIONS (MF=3) TO 20 MEV. IF THE TABULATED Fixup

CROSS SECTION ENDS BELOW 20 MEV IT WILL BE EXTENDED TO 20 MEV Fixup

AS EITHER ZERO (IMOPS(3)=1) OR CONSTANT (IMOPS(3)=2) EQUAL Fixup

TO THE LAST TABULATED VALUE. Fixup

(4) ALLOW REACTION (MF=3, ANY MT) DELETION. ALL SPECIFIED Fixup

REACTIONS WILL BE DELETED WHEN THE DATA IS READ FROM THE Fixup

INPUT ENDF/B DATA FILE AND WILL NOT BE IN THE OUTPUT ENDF/B Fixup

DATA FILE. WARNING DELETED REACTIONS MAY NOT BE USED TO DEFINE Fixup

ANY RECONSTRUCTED REACTIONS (I.E. REACTIONS DEFINED BY SUMMING Fixup

OTHER REACTIONS). SINCE DELETED REACTIONS ARE DELETED DURING Fixup

READING IT IS AS IF THEY NEVER EXISTED AND IF ANY DELETED Fixup

REACTION IS REQUIRED LATER TO DEFINE ANY SUM AN ERROR WILL Fixup

RESULT. THE USER MAY SPECIFY THAT THE DELETION RULES ARE TO BE Fixup

READ FROM INPUT (IMOPS(4)=1) OR THAT THE BUILT IN SUMMATION Fixup

RULES ARE TO BE USED (MOPS(4)=2). AT THE PRESENT TIME THE Fixup

BUILT-IN DELETION RULES ARE THAT NO SECTIONS SHOULD BE DELETED Fixup

(THE USER MAY OVERRIDE THIS CONVENTION BY INPUT). Fixup

(5) ALLOW REACTION (MF=3, ANY MT) RECONSTRUCTION BY SUMMING OTHER Fixup

REACTIONS. IN ORDER TO OPTIMIZE THE RUNNING TIME OF THIS Fixup

PROGRAM CARE SHOULD BE EXERCISED TO MINIMIZE THE NUMBER OF Fixup

TIMES THAT EACH CONTRIBUTING CROSS SECTION MUST BE USED. Fixup

THE USED MAY SPECIFY THAT THE SUMMATION RULES ARE TO BE READ Fixup

AS INPUT (IMOPS(5)=1) OR THAT THE BUILT IN SUMMATION RULES Fixup

ARE TO BE USED (IMOPS(5)=2). THE BUILT IN SUMMATION RULES ARE Fixup

DESIGNED TO USE ENDF/B CONVENTIONS AND TO MINIMIZE THE NUMBER Fixup

OF TIMES THAT EACH CROSS SECTION IS USED. Fixup

(6) INSURE THAT ALL CROSS SECTIONS ARE NON-NEGATIVE (I.E. ARE Fixup

ZERO OR POSITIVE). DURING READING ALL NEGATIVE CROSS SECTIONS Fixup

WILL BE SET EQUAL TO ZERO AND TREATED AS SUCH DURING ALL Fixup

SUBSEQUENT SUMMATIONS AND ENDF/B OUTPUT. Fixup

NOTE...THIS OPTION SHOULD NEVER BE USED WITH DATA CONTAINING Fixup

BACKGROUND CROSS SECTIONS WHICH MAY BE NEGATIVE. ONLY AFTER Fixup

THE RESONANCE CONTRIBUTION HAS BEEN ADDED TO THE BACKGROUND Fixup

TO DEFINE THE ACTUAL CROSS SECTION IS IT VALID TO ELIMINATE Fixup

NEGATIVE CROSS SECTIONS. Fixup

NOTE...THIS OPTION MAY BE USED TO DELETE NEGATIVE ELASTIC Fixup

CROSS SECTIONS THAT MAY RESULT FROM RECONSTRUCTING CROSS Fixup

SECTIONS FROM SINGLE LEVEL BREIT-WIGNER PARAMETERS. IF THE Fixup

TOTAL CROSS SECTION IS THEN RECONSTRUCTED USING THE CORRECTED Fixup

ELASTIC CROSS SECTION THE TOTAL WILL BE POSITIVE DUE TO THE Fixup

CONTRIBUTIONS OF CAPTURE AND FISSION (THUS AVOIDING NUMERICAL Fixup

INSTABILITY PROBLEMS DURING SELF-SHIELDING CALCULATIONS). Fixup

(7) WITHIN EACH SECTION OF CROSS SECTIONS DELETE ENERGIES THAT Fixup

ARE NOT IN ASCENDING ENERGY ORDER (ENERGY REPETITION IS O.K.) Fixup

(8) WITHIN EACH SECTION OF CROSS SECTIONS ELIMINATE DUPLICATE Fixup

POINTS (SUCCESSIVE POINTS WITH THE SAME ENERGY-CROSS SECTION). Fixup

(9) TEST THAT ALL SECTIONS ARE IN ASCENDING MAT/MF/MT ORDER. Fixup

IF NOT, NO CORRECTIVE ACTION WILL BE TAKEN, ONLY AN ERROR Fixup

MESSAGE WILL BE OUTPUT. Fixup

(10) CHECK MF/MT FOR EACH SECTION TO INSURE THAT THEY ARE DEFINED Fixup

IN THE ENDF/B FORMAR MANUAL. IF THEY ARE NOT DEFINED AN ERROR Fixup

MESSAGE IS PRINTED, BUT NO CORRECTIVE ACTION IS TAKEN. Fixup

(11) ALLOW SECTIONS WHICH ARE NOT PRESENT IN THE ORIGINAL (INPUT) Fixup

EVALUATION TO BE CREATED. NORMALLY THIS PROGRAM WILL ONLY Fixup

RECONSTRUCT AND OUTPUT SECTIONS IF THE SECTION IS PRESENT Fixup

IN THE ORIGINAL EVALUATION. THIS PROCEDURE IS FOLLOWED BECAUSE Fixup

NORMALLY THE PROGRAM DOES NOT KNOW HOW TO DEFINE THE CONTENTS Fixup

OF THE FIRST TWO LINES OF THE SECTION (E.G., Q-VALUE, Fixup

TEMPERATURE, INITIAL AND FINAL STATES). THIS OPTION MAY BE Fixup

USED TO ALLOW THE PROGRAM TO READ AND SAVE A TABLE DEFINING Fixup

THE CONTENTS OF THE FIRST TWO LINES OF EACH SECTION TO BE Fixup

CREATED. Fixup

NOTE...IF A SECTION IS PRESENT ANY COMMAND TO CREATE IT WILL Fixup

BE IGNORED. Fixup

(12)ALLOW ENERGY POINTS TO BE INSERTED. THE PROGRAM CAN READ UP Fixup

TO 50, ENERGIES, MAT, MT AND USE LINEAR INTERPOLATION TO Fixup

INSERT ENERGY POINTS INTO TABLES AS THEY ARE READ, E.G., Fixup

INSERT AN ENERGY POINT AT THERMAL ENERGY (0.0253 EV). IF Fixup

AN MAT AND/OR MT IS ZERO THIS IMPLIES = ALL - INSERT THE Fixup

ENERGY IN ALL TABLES. Fixup

(13)PUT ALLOW CROSS SECTIONS ON A UNIFORM ENERGY GRID = EACH Fixup

SECTION (MT) OF CROSS SECTIONS WILL INCLUDE ALL ENERGIES Fixup

WHICH APPEAR IN AT LEAST ONE SECTION OF DATA. PARAMETERS Fixup

(MT=251 THROUGH 255) ARE NOT INCLUDED IN THE UNIFORM ENERGY Fixup

GRID. Fixup

(14)DELETE SECTION IF CROSS SECTION = 0 AT ALL ENERGIES. THIS Fixup

SOUNDS LIKE AN ABSURD OPTION, BUT IS REQUIRED BECAUSE SUCH Fixup

SECTIONS EXIST IN ENDF/B-VI. Fixup

Fixup

CREATING RATIOS AND PRODUCTS Fixup

============================ Fixup

IN ORDER TO CREATE RATIOS AND PRODUCTS = NEW MT NUMBERS, YOU MUST Fixup

DO TWO THINGS, Fixup

Fixup

1) DEFINE EACH NEW MT NUMBER AS A RATIO OR PRODUCT OF TWO MT Fixup

NUMBERS. Fixup

Fixup

2) USE THE CREATE MT NUMBER OPTION AND INPUT THE FIRST TWO LINES Fixup

OF THE SECTION Fixup

Fixup

WARNING - UNLESS YOU DO BOTH OF THESE YOU WILL NOT OBTAIN OUTPUT Fixup

IN THE ENDF/B FORMAT. Fixup

Fixup

TWO SPECIAL MT NUMBERS HAVE BEEN DEFINED BY CSEWG INVOLVING Fixup

RATIOS AND PRODUCTS, Fixup

Fixup

ALPHA (MT=254)= CAPTURE (MT=102)/FISSION (MT=18) Fixup

Fixup

ETA (MT=255) = NU-BAR (MT=452)*FISSION (MT=18)/ABSORPTION (MT=27) Fixup

Fixup

ABSORPTION (MT=27) = FISSION (MT=18) + SUM (MT=102 THROUGH 116) Fixup

Fixup

AS YET THERE IS NO STANDARD DEFINITION OF MT NUMBERS FOR RATIO Fixup

OR PRODUCT DATA. YOU ARE FREE TO USE ANY MT NUMBERS NORMALLY NOT Fixup

USED IN THE ENDF/B. HOWEVER, IT WILL THEN BE YOUR RESPONSIBILITY Fixup

TO PROPERLY INTERPRET THE RESULTS, I.E., NOBODY ELSE WILL HAVE Fixup

ANY IDEA HOW TO INTERPRET A TABLE OF DATA ASSOCIATED WITH THE MT Fixup

NUMBERS YOU HAVE USED. Fixup

Fixup

THIS PROGRAM CAN BE ONLY DIRECTLY DEFINE RATIOS AND PRODUCTS Fixup

USING TWO MT NUMBERS = BINARY OPERATIONS, E.G., DEFINE THE CAPTURE Fixup

TO FISSION RATIO, OR DEFINE THE PRODUCT NU-BAR*FISSION. Fixup

Fixup

THIS PROGRAM CANNOT DIRECTLY DEFINE RATIO OR PRODUCT OF A SUM OF Fixup

SECTIONS TO THE SUM OF ANOTHER SET OF SECTIONS. HOWEVER, THIS CAN Fixup

BE DONE INDIRECTLY BY FIRST DEFINING A DUMMY MT NUMBER (ANY MT Fixup

NUMBER NOT NORMALLY USED IN ENDF/B) TO BE A SUM OF SECTIONS AND Fixup

A SECOND DUMMY MT NUMBER TO BE A SECOND SUM OF SECTIONS. YOU CAN Fixup

THEN DEFINE RATIO OR PRODUCT YOU REQUIRE TO BE THE RATIO OF THESE Fixup

TWO DUMMY MT NUMBERS. Fixup

Fixup

FOR EXAMPLE, TO DEFINE ETA, Fixup

1) FIRST DEFINE (MT=27) = (MT=27) + (SUM OF MT=102 THROUGH 116) Fixup

2) NEXT DEFINE (MT=333) = (MT=452)*(MT=18) Fixup

3) LAST DEFINE (MT=255) = (MT=333)/(MT=27) Fixup

DO NOT FORGET TO TURN ON THE CREATE SECTION OPTION (ON THE FIRST Fixup

INPUT LINE) AND INPUT THE FIRST TWO LINES OF SECTION MT=255 - Fixup

OTHERWISE YOU WILL NOT GET ANY ENDF/B FORMATTED OUTPUT. Fixup

Fixup

THE ONLY SPECIAL CONVENTIONS USED BY THIS PROGRAM IN CALCULATING Fixup

RATIOS ARE WHEN THE DENOMINATOR OF THE RATIO IS ZERO. IN THIS Fixup

CASE IF THE NUMERATOR IS ALSO ZERO THE RATIO IS DEFINED TO BE ONE. Fixup

IN THIS CASE IF THE NUMERATOR IS NOT ZERO THE RATIO IS DEFINED Fixup

TO BE ZERO. Fixup

Fixup

ENDF/B FORMAT Fixup

============= Fixup

THIS PROGRAM MAY BE USED WITH DATA IN ANY VERSION OF THE ENDF/B Fixup

FORMAT (I.E. ENDF/B-I, II, III, IV, V OR VI FORMAT). SINCE A Fixup

PAGING SYSTEM IS USED STORE CROSS SECTION TABLES ON SCRATCH FILES Fixup

THERE IS NO LIMIT TO THE SIZE OF TABLES (E.G. THE TOTAL CROSS Fixup

SECTION MAY BE REPRESENTED BY 200,000 TABULATED POINTS). Fixup

Fixup

WARNING Fixup

======= Fixup

(1) FOR EACH SECTION OF CROSS SECTIONS (I.E. EACH MT, MF=3) IN Fixup

THE ORIGINAL EVALUATION (I.E. ENDF/B DATA READ) ONE SECTION Fixup

OF DATA WILL BE OUTPUT, UNLESS THE SECTION HAS BEEN DELETED. Fixup

THIS INCLUDES ANY SECTIONS WHICH ARE NOT PRESENT IN THE Fixup

ORIGINAL EVALUATION, BUT THE USER INDICATES (BY INPUT) SHOULD Fixup

BE CREATED. Fixup

Fixup

THE PROGRAM WILL NOT OUTPUT ANY SECTION RECONSTRUCTED BY Fixup

SUMMATION UNLESS THE CORRESPONDING SECTION (MT NUMBER) IS Fixup

PRESENT IN THE ORIGINAL EVALUATION OR USER INPUT INDICATES Fixup

SHOULD BE CREATED AND OUTPUT. THIS IS (A) BECAUSE THE Fixup

PROGRAM CANNOT DEFINE THE PARAMETERS TO APPEAR ON THE FIRST Fixup

TWO LINES OF THE SECTION, (B) TO AVOID OUTPUTTING TOO MUCH Fixup

DATA WHICH THE USER MAY NOT BE INTERESTED IN. Fixup

Fixup

(2) FOR ANY SECTIONS THAT DO NOT APPEAR IN THE ORIGINAL DATA THE Fixup

USER MAY SPECIFY THAT THEY BE DEFINED BY SUMMATION. ANY SUCH Fixup

SECTION MAY BE USED BE DEFINE SUBSEQUENT SUMS, BUT THE SECTION Fixup

ITSELF WILL NOT BE OUTPUT (E.G. GENERALLY MT=27 AND 101 ARE Fixup

NOT PRESENT IN EVALUATIONS. HOWEVER, THE BUILT-IN SUMMATION Fixup

RULES OF THIS PROGRAM USES THE ENDF/B SUMMATION RULES TO Fixup

DEFINE MT=27 AND 101, WHICH IN TURN ARE USED TO DEFINE THE Fixup

NON-ELASTIC CROSS SECTION, MT=3. SECTIONS MT=27 AND 101 ARE Fixup

NOT OUTPUT). Fixup

Fixup

(3) ALL DATA IN FILE 3 AND 23 MUST BE LINEARLY INTERPOLABLE. IF Fixup

THE DATA IS NOT LINEARLY INTERPOLABLE THIS PROGRAM WILL Fixup

TERMINATE. Fixup

Fixup

PROGRAM OPERATION Fixup

================= Fixup

ALL MAT NUMBER ON AN ENDF/B TAPE ARE PROCESSED. EACH MAT IS Fixup

TREATED SEPARATELY. WITHIN EACH MAT, EACH SECTION BEFORE MF=3 Fixup

IS READ, CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT. Fixup

WHEN MF=3 IS LOCATED ALL CROSS SECTIONS ARE READ, SECTIONS TO BE Fixup

DELETED ARE DELETED, SECTIONS WHICH ARE NOT PRESENTED AND USER Fixup

INPUT INDICATES SHOULD BE CREATED ARE CREATE, SECTIONS TO BE KEPT Fixup

ARE CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND WRITTEN TO A Fixup

SCRATCH FILE. NEXT, IF THE USER SPECIFIES THAT THEY SHOULD, Fixup

SECTIONS ARE RECONSTRUCTED. FINALLY ALL CROSS SECTIONS (OLD AND Fixup

NEW) ARE OUTPUT. WITHIN THE SAME MAT, EACH SECTION AFTER MF=3 IS Fixup

READ, CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT. Fixup

Fixup

MF=3 Fixup

==== Fixup

THE TREATMENT OF THE CROSS SECTIONS REQUIRES UP TO 4 PASSES FOR Fixup

CROSS SECTIONS. IN THE PROGRAM THEY CORRESPOND TO SUBROUTINES Fixup

PASS1, PASS2, PASS3 AND PASS4. THE ORIGINAL AND FINAL ENDF/B DATA Fixup

FILES, 5 SCRATCH FILES AND 3 IN CORE ARRAYS ARE USED. OPERATIONS Fixup

PERFORMED DURING EACH PASS ARE, Fixup

Fixup

PASS1 Fixup

===== Fixup

READ ALL CROSS SECTIONS FROM ITAPE. DELETED ANY SECTIONS. CREATE Fixup

ANY SECTIONS. CHECK/CORRECT THEM AND WRITE THEM TO SCRATCH FILE. Fixup

DATA IS READ INTO ARRAY A, TRANSFERRED TO ARRAY C (AFTER EDITING) Fixup

AND OUTPUT TO ISCRC FROM ARRAY C. Fixup

ITAPE - UNIT ORIGINAL ENDF/B DATA IS READ FROM. Fixup

ISCRC - SCRATCH UNIT THAT EDITED DATA IS WRITTEN ON. Fixup

TABA - ARRAY INTO WHICH ORIGINAL DATA IS READ. Fixup

TABC - ARRAY INTO WHICH EDITED DATA IS TRANSFERRED TO AND Fixup

FROM WHICH IT IS WRITTEN TO ISCRC. Fixup

Fixup

PASS2 Fixup

===== Fixup

IF A UNIFORM ENERGY GRID IS REQUESTED IT IS CREATED DURING THIS Fixup

PASS. FIRST ALL OF THE CROSS SECTIONS FROM PASS1 ARE READ AND A Fixup

UNIFORM ENERGY GRID IS CREATED = ALL ENERGIES THAT ARE INCLUDED Fixup

IN AT LEAST ONE SECTION (MT) OF CROSS SECTIONS. Fixup

ISCRA - SCRATCH UNIT CONTAINING UNIFORM ENERGY GRID. Fixup

ISCRB - SCRATCH UNIT CONTAINING UNIFORM ENERGY GRID. Fixup

ISCRC - SCRATCH UNIT THAT EDITED DATA IS READ FROM. Fixup

TABA - ARRAY CONTAINING UNIFORM ENERGY GRID. Fixup

TABB - ARRAY CONTAINING UNIFORM ENERGY GRID. Fixup

TABC - ARRAY CONTAINING EDITED DATA. Fixup

Fixup

THE UNIFORM ENERGY GRID ENDS UP ON ISCRB. NEXT EACH SECTION OF Fixup

CROSS SECTIONS FROM PASS1 IS READ FROM ISCRC, INTERPOLATED TO Fixup

THE UNIFORM ENERGY GRID AND OUTPUT TO ISCRA. FINALLY ISCRA AND Fixup

ISCRC ARE SWITCH, SO THAT AT THE END OF THIS PASS THE DATA WILL Fixup

AGAIN BE ON ISCRC (EXACTLY AS AT THE END OF PASS1), WITH UPDATED Fixup

POINT COUNTS. Fixup

ISCRA - SCRATCH UNIT THAT UNIFORM ENERGY GRID DATA IS WRITTEN ON. Fixup

ISCRB - SCRATCH UNIT CONTAINING UNIFORM ENERGY GRID. Fixup

ISCRC - SCRATCH UNIT THAT EDITED DATA IS READ FROM. Fixup

TABA - ARRAY CONTAINING UNIFORM ENERGY GRID DATA. Fixup

TABB - ARRAY CONTAINING UNIFORM ENERGY GRID. Fixup

TABC - ARRAY CONTAINING EDITED DATA. Fixup

Fixup

PASS3 Fixup

===== Fixup

SUMMATION CROSS SECTIONS ARE DEFINED BY READING DATA FROM ISCRC Fixup

AND MERGING THEM ONTO ISCRA. THE FIRST SECTION THAT CONTRIBUTES Fixup

TO A SUM IS MERELY COPIED FROM C TO A. IF MORE SECTIONS WILL Fixup

CONTRIBUTE TO THE SUM THE DATA IN A IS TRANSFERRED TO B, A Fixup

SECTION OF DATA FROM C IS ADDED TO THE DATA IN B AND STORED IN Fixup

A. THE CYLE OF ADDED C AND B TO A, FOLLOWED BY MOVING A TO B Fixup

IS CONTINUED UNTIL ALL CONTRIBUTING SECTIONS HAVE BEEN ADDED. Fixup

THE SUM IS THEN COPIED FROM A TO D. IF NEWLY CONSTRUCTED SECTION Fixup

IS REQUIRED FOR ANY LATER SUMMUATIONS IT IS ALSO COPIED TO E. Fixup

THE CYCLE OF ADDED SECTIONS FROM C AND B TO A IS REPEATED FOR Fixup

EACH REQUIRED SUMMATION REACTION. IN ADDITION TO SECTIONS FROM Fixup

C, AFTER THE FIRST SUMMATION SECTIONS MAY ALSO BE ADDED TO A Fixup

FROM E (THE CONTRIBUTION OF NEW RECONSTRUCTED CROSS SECTIONS). Fixup

WHEN ALL REQUIRED SECTIONS HAVE BEEN RECONSTRUCTED THE NEW Fixup

SECTIONS WILL BE ON E AND THE ORIGINAL SECTIONS ON C. Fixup

ISCRC - SCRATCH FILE FROM WHICH ORIGINAL DATA IS READ. Fixup

ISCRA - SCRATCH FILE ONTO WHICH SUM FOR ONE SECTION IS WRITTEN. Fixup

ISCRD - SCRATCH FILE ONTO WHICH ALL SUM CROSS SECTIONS ARE Fixup

WRITTEN. Fixup

ISCRE - SCRATCH FILE ONTO WHICH ALL SUM CROSS SECTIONS WHICH Fixup

ARE REQUIRED FOR LATER SUMS ARE WRITTEN. Fixup

ISCRB - UTILITY SCRATCH FILE USED TO CREATE SUM CROSS SECTIONS. Fixup

TABA - ARRAY INTO WHICH SUMS ARE WRITTEN. Fixup

TABB - ARRAY INTO WHICH PARTIAL SUMS ARE WRITTEN. Fixup

TABC - ARRAY INTO WHICH ORIGINAL DATA IS READ. Fixup

Fixup

PASS4 Fixup

===== Fixup

CROSS SECTIONS ARE READ FROM ISCRC (ORIGINAL) AND ISCRD (NEW) Fixup

AND ARE WRITTEN IN THE ENDF/B FORMAT ON OTAPE. THE BEGINNING OF Fixup

EACH SECTION OF ORIGINAL DATA IS READ FROM ISCRC (TO DEFINE Fixup

SECTION HEADER INFORMATION). IF THIS MT HAS NOT BEEN RECOSTRUCTED Fixup

ON ISCRD THE ORIGINAL SECTION IS OUTPUT. IF THE SECTION HAS BEEN Fixup

RECONSTRUCTED THE ORIGINAL SECTION IS SKIPPED AND THE NEW SECTION Fixup

IS OUTPUT. Fixup

OTAPE - OUTPUT DATA IN THE ENDF/B FORMAT. Fixup

ISCRC - SCRATCH FILE FROM WHICH ORIGINAL DATA IS READ. Fixup

ISCRD - SCRATCH FILE FROM WHICH NEW DATA IS READ. Fixup

TABC - ARRAY INTO WHICH CROSS SECTIONS ARE READ FROM SCRATCH Fixup

AND WRITTEN TO OTAPE Fixup

Fixup

I/O FILE DEFINITIONS Fixup

==================== Fixup

UNIT DESCRIPTION Fixup

==== =========== Fixup

2 INPUT PARAMETERS. Fixup

3 OUTPUT REPORT. Fixup

10 ORIGINAL DATA IN THE ENDF/B FORMAT. Fixup

11 FINAL DATA IN THE ENDF/B FORMAT. Fixup

12 SCRATCH FILE Fixup

14 SCRATCH FILE Fixup

15 SCRATCH FILE Fixup

16 SCRATCH FILE Fixup

17 SCRATCH FILE Fixup

Fixup

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Fixup

=============================================================== Fixup

UNIT FILE NAME FORMAT Fixup

==== ========== ====== Fixup

2 FIXUP.INP BCD Fixup

3 FIXUP.LST BCD Fixup

10 ENDFB.IN BCD Fixup

11 ENDFB.OUT BCD Fixup

12-17 (SCRATCH) BINARY Fixup

Fixup

INPUT LINES Fixup

=========== Fixup

LINE COLUMNS FORMAT DESCRIPTION Fixup

==== ======= ====== =========== Fixup

1 1-14 14I1 INPUT OPTIONS AS DESCRIBED ABOVE. Fixup

EACH COLUMN OF THE INPUT LINE CONTROLS Fixup

ONE OF THE TESTS/CORRECTIONS DESCRIBED Fixup

ABOVE. TESTS/CORRECTION 1-14 (NOT ALL Fixup

IMPLEMENTED YET) CORRESPOND TO COLUMNS Fixup

1-14 OF THIS INPUT LINE AND ARE TREATED Fixup

AS FOLLOWS, Fixup

= 0 - DO NOT PERFORM TEST/CORRECTION. Fixup

= 1 - PERFORM TEST/CORRECTION. Fixup

FOR MT EXCLUSION FROM THRESHOLD TESTS Fixup

(COLUMN 2), DELETION (COLUMN 4), OR Fixup

SUMMATION (COLUMN 5) THE INPUT OPTION Fixup

MAY BE, Fixup

= 1 - READ RULES FROM INPUT Fixup

= 2 - USE BUILT-IN RULES Fixup

2 1-60 A60 ENDF/B INPUT DATA FILENAME Fixup

(STANDARD OPTION = ENDFB.IN) Fixup

3 1-60 A60 ENDF/B OUTPUT DATA FILENAME Fixup

(STANDARD OPTION = ENDFB.OUT) Fixup

4-M 1-5 FREE CHARACTER (S,D,T,R,*) FOLLOWED BY BLANK OR Fixup

FORM MT NUMBER Fixup

- THE ALLOWED CHARACTERS ARE, Fixup

- S OR BLANK = SUM (OR DIFFERENCES) Fixup

- D = DELETE Fixup

- T = NO THRESHOLD ENERGY CORRECTIONS Fixup

- R = RATIO Fixup

- * = PRODUCT Fixup

6-72 FREE UP TO 10 LOWER AND UPPER MT RANGES WHICH Fixup

FORM WILL BE USED TO DEFINE THE RECONSTRUCTED Fixup

CROSS SECTION OR TO DEFINE MT RANGES WHICH Fixup

ARE EXCLUDED FROM THRESHOLD TESTS. Fixup

Fixup

EACH MT NUMBER IS DEFINED BY A CONTINUOUS Fixup

STRING OF DIGITS, POSSIBILITY PRECEEDED BY Fixup

A - (MINUS SIGN). EACH MT NUMBER MUST BE Fixup

BLANK OR OTHERWISE (NOT A DIGIT) DELIMITED. Fixup

Fixup

COLUMNS 6-72 MAY CONTAIN STRINGS OF DIGITS Fixup

THE FIRST DIGIT STRING OF EACH PAIR MAY BE Fixup

PRECEEDED BY A - (MINUS SIGN). Fixup

Fixup

EACH LINE WILL BE INTERPRETED AS FOLLOWS, Fixup

Fixup

*SUMMATION (OR DIFFERENCES) Fixup

-------------------------- Fixup

COLUMNS 1-5 = S OR BLANK FOLLOWED BY THE Fixup

MT NUMBER TO BE DEFINED BY SUMMATION Fixup

Fixup

COLUMNS 6-72 = UP TO 10 MT RANGE (PAIRS OF Fixup

MT NUMBERS) TO BE USED TO DEFINED THE SUM. Fixup

IF THE FIRST MT NUMBER OF A PAIR IS Fixup

NEGATIVE THE RANGE OF MT NUMBERS IS Fixup

SUBTRACTED - AT LEAST ONE RANGE MUST BE Fixup

SPECIFIED. Fixup

Fixup

*DELETIONS Fixup

--------- Fixup

COLUMNS 1-5 = D FOLLOWED BY BLANKS Fixup

Fixup

COLUMNS 6-72 CONTAIN UP TO 10 MT RANGE Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING Fixup

A RANGE OF MT NUMBERS TO BE DELETED - AT Fixup

LEAST ONE RANGE MUST BE SPECIFIED. Fixup

Fixup

*EXCLUSION FROM THRESHOLD TESTS Fixup

------------------------------ Fixup

COLUMNS 1=5 = T FOLLOWED BY BLANKS Fixup

Fixup

COLUMNS 6-72 CONTAIN UP TO 10 MT RANGE Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING Fixup

A RANGE OF MT NUMBERS WHOSE THRESHOLD Fixup

ENERGY WILL NOT BE CHECKED - AT LEAST ONE Fixup

RANGE MUST BE SPECIFIED. Fixup

Fixup

*RATIO Fixup

----- Fixup

COLUMNS 1-5 = R FOLLOWED BY THE MT NUMBER Fixup

TO BE DEFINED BY A RATIO Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE Fixup

USED TO DEFINE THE RATIO. Fixup

Fixup

*PRODUCT Fixup

----- Fixup

COLUMNS 1-5 = * FOLLOWED BY THE MT NUMBER Fixup

TO BE DEFINED BY A PRODUCT Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE Fixup

USED TO DEFINE THE PRODUCT. Fixup

Fixup

CONVENTIONS Fixup

----------- Fixup

*UP TO 20 DELETIONS AND 20 SUMMATIONS OR Fixup

RATIOS OR PRODUCTS MAY BE SPECIFIED. Fixup

*ONLY 1 EXCLUSION FROM THRESHOLD TESTS Fixup

MAY BE SPECIFIED (THE 1 LINE MAY CONTAIN Fixup

UP TO 10 MT RANGES TO EXCLUDE FROM TESTS). Fixup

*INPUT IS TERMINATED BY INPUTTNG 0 OR Fixup

BLANK IN COLUMNS 1-72 (I.E. THE LAST Fixup

INPUT LINE MUST BE BLANK). Fixup

*THE UPPER LIMIT OF EACH RANGE MUST BE AT Fixup

LEAST AS BIG AS THE LOWER LIMIT (IN Fixup

ABSOLUTE VALUE). Fixup

*FOR RECONSTRUCTION POSITIVE MT RANGES WILL Fixup

BE ADDED TO THE SUM AND NEGATIVE MT RANGES Fixup

WILL BE SUBTRACTED. Fixup

*IF INPUT OPTION 2 (FIRST INPUT LINE) IS Fixup

0 THRESHOLD EXCLUSION IS NOT ALLOWED. Fixup

*IF INPUT OPTION 4 (FIRST INPUT LINE) IS Fixup

0 DELETIONS ARE NOT ALLOWED. Fixup

*IF INPUT OPTION 5 (FIRST INPUT LINE) IS Fixup

0 SUMMATIONS AND RATIOS ARE NOT ALLOWED. Fixup

N-K IF THE USER SPECIFIES THAT SECTIONS WHICH Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION Fixup

MAY BE CREATED, TWO LINES MUST BE INPUT FOR Fixup

EACH SECTION TO BE CREATED. THE TWO LINES Fixup

DEFINE (C1, C2, L1 AND L2) FOR EACH OF THE Fixup

FIRST TWO LINES OF THE SECTION TO BE Fixup

CREATED. THE FIRST LINE ALSO DEFINES (MAT Fixup

AND MT). (N1, N2) ARE ALWAYS ZERO ON THE Fixup

FIRST LINE AND WILL BE CALCULATED BY THE Fixup

PROGRAM FOR THE SECOND LINE. Fixup

FIRST 1-11 E11.4 ZA OF SECTION TO BE CREATED Fixup

LINE 12-22 E11.4 AWRE OF SECTION TO BE CREATED Fixup

23-33 I11 L1 OF SECTION TO BE CREATED Fixup

34-44 I11 L2 OF SECTION TO BE CREATED Fixup

45-48 I4 MAT OF SECTION TO BE CREATED Fixup

49-51 I3 MT OF SECTION TO BE CREATED Fixup

SECOND 1-11 E11.4 C1 OF SECTION TO BE CREATED Fixup

LINE 12-22 E11.4 C2 OF SECTION TO BE CREATED Fixup

23-33 I11 L1 OF SECTION TO BE CREATED Fixup

34-44 I11 L2 OF SECTION TO BE CREATED Fixup

*PAIRS OF LINES MAY BE IN ANY MAT/MT ORDER Fixup

(E.G., THEY NEED NOT BE IN ASCENDING Fixup

MAT/MT ORDER). Fixup

*UP TO 50 PAIRS OF LINES MAY BE USED TO Fixup

DEFINE SECTIONS TO BE CREATED. THE LIST Fixup

IS TERMINATED WHEN THE FIRST LINE OF A Fixup

PAIR CONTAINS A ZERO (OR BLANK) MAT AND/OR Fixup

MT. Fixup

M-N IF THE USER SPECIFIES THAT ENERGIES WHICH Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION Fixup

MAY BE INSERTED, ONE LINE MUST BE INPUT FOR Fixup

EACH ENERGY TO BE INSERTED. Fixup

1-11 E11.4 ENERGY TO BE INSERTED Fixup

12-15 I4 MAT IN WHICH TO INSERT ENERGY = 0 = ALL Fixup

16-18 I3 MT IN WHICH TO INSERT ENERGY = 0 = ALL Fixup

*UP TO 50 (ENERGY, MAT, MT) LINES MAY BE Fixup

USED. THE LIST IS TERMINATED BY A BLANK Fixup

LINE. Fixup

*INPUT MAY BE IN ANY (ENERGY, MAT, MT) Fixup

ORDER. Fixup

*ENERGY POINTS CAN ONLY BE INSERTED WITHIN Fixup

THE ORIGINAL ENERGY RANGE OF A SECTION - Fixup

THIS OPTION CANNOT BE USED TO EXTEND THE Fixup

CROSS SECTION EITHER BELOW OR ABOVE THE Fixup

ORIGINAL TABULATED ENERGY RANGE. Fixup

Fixup

EXAMPLE INPUT NO. 1 Fixup

=================== Fixup

(1) USE OPTIONS 1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS) Fixup

(2) DELETE MT=900 (FOR EXAMPLE PURPOSES ONLY) Fixup

(3) DEFINE THE FOLLOWING MT NUMBERS TO BE RECONSTRUCTED, Fixup

(MT= 4) = THE SUM OF MT= 51 THROUGH 91 Fixup

(MT=103) = THE SUM OF MT=700 THROUGH 718 (NOT 719) Fixup

(MT=104) = THE SUM OF MT=720 THROUGH 738 (NOT 739) Fixup

(MT=105) = THE SUM OF MT=740 THROUGH 758 (NOT 759) Fixup

(MT=106) = THE SUM OF MT=760 THROUGH 778 (NOT 779) Fixup

(MT=107) = THE SUM OF MT=780 THROUGH 798 (NOT 799) Fixup

(MT=101) = THE SUM OF MT=102 THROUGH 114 Fixup

(MT= 18) = (MT=19) + (MT=20 AND 21) + (MT=38) Fixup

(IF TOTAL FISSION, MT=18, IS NOT PRESENT, DEFINE Fixup

IT BY SUMMING FIRST, SECOND, ETC. CHANCE - NOTE Fixup

THAT THIS MUST BE DONE IN THIS ORDER, SINCE THE Fixup

NEXT SUM INVOLVES USING MT=18. Fixup

(MT= 27) = THE SUM OF MT= 18 AND 101 Fixup

(MT=101 RECONSTRUCTED ABOVE USED IN SUM). Fixup

(MT= 3) = THE SUM OF (MT=4)+(MT=6-9)+(MT=16-17)+(MT=22-37)+ Fixup

(MT=41-45) Fixup

(MT=4 AND 27 RECONSTRUCTED ABOVE USED IN SUM). Fixup

(MT= 19) = (MT=18) - (MT=20 AND 21) - (MT=38) Fixup

(DEFINE FIRST CHANGE FISSION BY SUBTRACTION TO Fixup

ALLOW RESONANCE CONTRIBUTION FROM MT=18 TO BE Fixup

INCLUDED IN MT=19). Fixup

(MT= 1) = THE SUM OF MT=2 AND 3 Fixup

(MT=3 RECONSTRUCTED ABOVE USED IN SUM). Fixup

(4) THRESHOLD ENERGIES OF THE FOLLOWING MT NUMBERS WILL NOT BE Fixup

TESTED OR CORRECTED. Fixup

MT=1, 4, 18, 19, 91, 103 THROUGH 114. Fixup

(5) DEFINE MT=254 TO BE THE CAPTURE TO FISSION RATIO (MT=102/18) Fixup

(6) CREATE MAT=1300/MT=254 - NOTE, THIS IS NECESSARY IN ORDER TO Fixup

HAVE THE CAPTURE TO FISSION RATIO OUTPUT IN THE ENDF/B FORMAT Fixup

Fixup

NOTE, ON THE FOLLOWING INPUT LINES THE CHARACTERS = ( ) + , HAVE Fixup

BEEN USED ONLY TO MAKE THE INPUT MORE READABLE - THESE CHARACTERS Fixup

WILL BE SKIPPED BY THE PROGRAM IN READING INPUT - THE RESULTS Fixup

WOULD BE THE SAME IF THESE CHARACTERS WERE OMITTED, AS LONG AS Fixup

ALL OF THE MT NUMBERS ARE DELIMITED, I.E., THERE IS AT LEAST ONE Fixup

NON-DIGITAL CHARACTER BETWEEN MT NUMBERS. NOTE, THAT - (MINUS Fixup

SIGN) IS IMPORTANT AND IS USED DURING INPUT TO DEFINE MT RANGES Fixup

WHICH SHOULD BE SUBTRACTED, E.,G., SEE THE DEFINITION OF MT=19. Fixup

Fixup

READ FILE /ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT Fixup

Fixup

THE FOLLOWING 21 INPUT LINES ARE REQUIRED. Fixup

Fixup

11111111111 Fixup

/ENDFB6/K300/LEAD.IN Fixup

/ENDFB6/K300/LEAD.OUT Fixup

D900 Fixup

4=( 51, 91) Fixup

103=(700,718) Fixup

104=(720,738) Fixup

105=(740,758) Fixup

106=(760,778) Fixup

107=(780,798) Fixup

101=(102,114) Fixup

18=( 19, 19)+( 20, 21)+( 38, 38) Fixup

27=( 18, 18)+(101,101) Fixup

3=( 4, 4)+( 6, 9)+( 16, 17)+( 22, 37)+( 41, 45) Fixup

19=( 18, 18)-( 20, 21)-( 38, 38) Fixup

1=( 2, 3) Fixup

T ( 1, 1) ( 4, 4) ( 18, 19) ( 91, 91) (103,114) Fixup

R254=(102/ 18) Fixup

(BLANK LINE TO TERMINATE SUMMATION/DELETION RULES) Fixup

2.00400+ 3 0.00000+ 0 0 01300254 Fixup

0.00000+ 0 0.00000+ 0 0 0 Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES) Fixup

Fixup

NOTE, THE DELETION AND THRESHOLD EXCLUSION LINES MAY APPEAR IN Fixup

IN ANY ORDER. HOWEVER, SUMMATION AND RATIO RULES MUST APPEAR IN Fixup

THE ORDER IN WHICH YOU WANT THEM TO BE EXECUTED - E.G., THE Fixup

ABOVE INPUT WILL FIRST RECONSTRUCT MT=4, WHICH CAN THEN BE USED Fixup

TO CONTRIBUTE TO THE FOLLOWING SUM TO DEFINE MT=3, WHICH IN TURN Fixup

CAN THEN BE USED TO CONTRIBUTE TO THE FOLLOWING SUM TO DEFINE Fixup

MT=1. IF THE ORDER OF THE INPUT LINES IS CHANGED SUCH THAT MT=3 Fixup

IS RECONSTRUCTED BEFORE MT=4, THE ORIGINAL MT=4 WILL BE USED IN Fixup

THE SUMMATION TO DEFINE MT=3. THE SAME RULES APPLY TO CALCULATING Fixup

RATIOS, IF EITHER THE NUMERATOR OR DENOMINATOR IS TO BE DEFINED Fixup

BY SUMMATION, THIS SHOULD BE DONE BEFORE DEFINING THE RATIO BY Fixup

INPUT PARAMETERS. Fixup

Fixup

EXAMPLE INPUT NO. 2 Fixup

=================== Fixup

(1) USE OPTIONS 1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS) Fixup

(2) USE BUILT-IN TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO Fixup

THE INPUT ABOVE UNDER EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS Fixup

WILL BE DELETED. Fixup

(3) IF NOT PRESENT, CREATE MAT=1300/MT=1 Fixup

Fixup

USE THE STANDARD FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE Fixup

DONE BY LEAVING THE SECOND AND THIRD INPUT LINES BLANK). Fixup

Fixup

THE FOLLOWING 6 INPUT LINES ARE REQUIRED. Fixup

Fixup

12122111111 Fixup

Fixup

Fixup

2.00400+ 3 0.00000+ 0 0 01300 1 Fixup

0.00000+ 0 0.00000+ 0 0 0 Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES) Fixup

Fixup

EXAMPLE INPUT NO. 3 Fixup

=================== Fixup

(1) USE OPTIONS 1-10 (ALL OPTIONS PRESENTLY IMPLEMENTED, EXCEPT Fixup

DO NOT ALLOW SECTION CREATION AND INSERT ENERGY POINTS). Fixup

(2) USE BUILT-IN TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO Fixup

THE INPUT ABOVE UNDER EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS Fixup

WILL BE DELETED. Fixup

(3) DO NOT CREATE ANY SECTIONS. Fixup

Fixup

READ FILE /ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT Fixup

Fixup

THE FOLLOWING 3 INPUT LINES ARE REQUIRED. Fixup

Fixup

1212211111 Fixup

/ENDFB6/K300/LEAD.IN Fixup

/ENDFB6/K300/LEAD.OUT Fixup

Fixup

EXAMPLE INPUT NO. 4 Fixup

=================== Fixup

SAME AS EXAMPLE NO. 3, ABOVE, EXCEPT INSERT AN ENERGY POINT AT Fixup

THERMAL FOR ALL REACTIONS WHICH SPAN THE THERMAL ENERGY RANGE. Fixup

Fixup

USE THE STANDARD FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE Fixup

DONE BY LEAVING THE SECOND AND THIRD INPUT LINES BLANK). Fixup

Fixup

THE FOLLOWING 5 INPUT LINES ARE REQUIRED. Fixup

Fixup

121221111101 Fixup

Fixup

Fixup

2.53000- 2 0 0 Fixup

(BLANK LINE TO TERMINATE ENERGY INSERTS) Fixup

Fixup

WARNING Fixup

======= Fixup

ALTHOUGH THIS PROGRAM IS DESIGNED TO ALLOW REACTIONS TO BE DEFINED Fixup

BY ADDING OR SUBTRACTING REACTIONS THE USER SHOULD ALWAYS TRY TO Fixup

DEFINE REACTIONS BY SUMMING TO AVOID NEGATIVE CROSS SECTIONS. FOR Fixup

EXAMPLE, IT IS POSSIBLE TO CALCULATE MT=3 AND DEFINE MT=1 AS THE Fixup

SUM OF MT=2 AND 3 (THE RECOMMENDED APPROACH AS USED IN THE ABOVE Fixup

INPUT). ALTERATIVELY IT IS POSSIBLE TO CALCULATE MT=1 AND DEFINE Fixup

MT=3 AS MT=1 MINUS MT=2 (THIS APPROACH IS NOT RECOMMENDED). Fixup

Fixup

THE ONLY BUILT-IN SUMMATION RULE THAT USES SUBTRACTION IS THE Fixup

CALCULATION OF THE FIRST CHANGE FISSION (MT=19) AS THE TOTAL Fixup

FISSION (MT=18) MINUS THE SECOND, THIRD AND FOURTH CHANGE FISSION Fixup

(MT=20, 21, 38). THIS HAS BEEN DONE TO ALLOW THE RESONANCE Fixup

CONTRIBUTION, CALCULATED BY MANY CODES AND INCLUDED IN MT=18, Fixup

TO BE CONSISTENTLY INCLUDED IN THE FIRST CHANCE FISSION. Fixup

Fixup

======================================================================= Fixup

======================================================================= Groupie

Groupie

PROGRAM GROUPIE Groupie

VERSION 76-1 (NOVEMBER 1976) Groupie

VERSION 79-1 (OCTOBER 1979) CDC-7600 AND CRAY-1 VERSION. Groupie

VERSION 80-1 (MAY 1980) IBM, CDC AND CRAY VERSION Groupie

VERSION 81-1 (JANUARY 1981) EXTENSION TO 3000 GROUPS Groupie

VERSION 81-2 (MARCH 1981) IMPROVED SPEED Groupie

VERSION 81-3 (AUGUST 1981) BUILT-IN 1/E WEIGHTING SPECTRUM Groupie

VERSION 82-1 (JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY Groupie

VERSION 83-1 (JANUARY 1983)*MAJOR RE-DESIGN. Groupie

*ELIMINATED COMPUTER DEPENDENT CODING. Groupie

*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Groupie

*NEW MULTI-BAND LIBRARY BINARY FORMAT. Groupie

VERSION 83-2 (OCTOBER 1983) ADDED OPTION TO ALLOW SIGMA-0 TO BE Groupie

DEFINED EITHER AS MULTIPLES OF Groupie

UNSHIELDED TOTAL CROSS SECTION IN EACH Groupie

GROUP, OR POWERS OF 10 IN ALL GROUPS. Groupie

VERSION 84-1 (APRIL 1984) ADDED MORE BUILT IN MULTIGROUP ENERGY Groupie

STRUCTURES. Groupie

VERSION 85-1 (APRIL 1985) *UPDATED FOR ENDF/B-VI FORMATS. Groupie

*SPECIAL I/O ROUTINES TO GUARANTEE Groupie

ACCURACY OF ENERGY. Groupie

*DOUBLE PRECISION TREATMENT OF ENERGY Groupie

(REQUIRED FOR NARROW RESONANCES). Groupie

*MINIMUM TOTAL CROSS SECTION TREATMENT Groupie

VERSION 85-2 (AUGUST 1985) *FORTRAN-77/H VERSION Groupie

VERSION 86-1 (JANUARY 1986)*ENDF/B-VI FORMAT Groupie

VERSION 86-2 (JUNE 1986) *BUILT-IN MAXWELLIAN, 1/E AND FISSION Groupie

WEIGHTING SPECTRUM. Groupie

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Groupie

FILE NAMES (SEE, SUBROUTINES FILIO1 Groupie

FILIO2 FOR DETAILS). Groupie

*IMPROVED BASED ON USER COMMENTS. Groupie

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Groupie

INSURE PROGRAM WILL NOT DO ANYTHING Groupie

CRAZY. Groupie

*UPDATED TO USE NEW PROGRAM CONVERT Groupie

KEYWORDS. Groupie

*ADDED LIVERMORE CIVIC COMPILER Groupie

CONVENTIONS. Groupie

VERSION 91-1 (JUNE 1991) *INCREASED PAGE SIZE FROM 1002 TO 5010 Groupie

POINTS Groupie

*UPDATED BASED ON USER COMMENTS Groupie

*ADDED FORTRAN SAVE OPTION Groupie

*COMPLETELY CONSISTENT ROUTINE TO READ Groupie

FLOATING POINT NUMBERS. Groupie

VERSION 92-1 (JANUARY 1992)*ADDED RESONANCE INTEGRAL CALCULATION - Groupie

UNSHIELDED AND/OR SHIELDED - FOR Groupie

DETAILS SEE BELOW Groupie

*INCREASED NUMBER OF ENERGY POINTS Groupie

IN BUILT-IN SPECTRA - TO IMPROVE Groupie

ACCURACY. Groupie

*ALLOW SELECTION OF ZA/MF/MT OR Groupie

MAT/MF/MT RANGES - ALL DATA NOT Groupie

SELECTED IS SKIPPED ON INPUT AND Groupie

NOT WRITTEN AS OUTPUT. Groupie

*COMPLETELY CONSISTENT I/O ROUTINES - Groupie

TO MINIMIZE COMPUTER DEPENDENCE. Groupie

*NOTE, CHANGES IN INPUT PARAMETER Groupie

FORMAT - FOR ZA/MF/MT OR MAT/MF/MT Groupie

RANGES. Groupie

VERSION 92-2 (JUNE 1992) *MULTIBAND PARAMETERS OUTOUT AS Groupie

CHARACTER (RATHER THAN BINARY) FILE. Groupie

VERSION 93-1 (APRIL 1993) *INCREASED PAGE SIZE FROM 5010 TO Groupie

30000 POINTS Groupie

*ELIMINATED COMPUTER DEPENDENCE. Groupie

VERSION 94-1 (JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES Groupie

TO ALLOW ACCESS TO FILE STRUCTURES Groupie

(WARNING - INPUT PARAMETER FORMAT Groupie

HAS BEEN CHANGED) Groupie

*CLOSE ALL FILES BEFORE TERMINATING Groupie

(SEE, SUBROUTINE ENDIT) Groupie

VERSION 95-1 (JANUARY 1994)*CORRECTED MAXWELLIAN WEIGHTING Groupie

*CHANGING WEIGHTING SPECTRUM FROM Groupie

0.1 TO 0.001 % UNCERTAINTY Groupie

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Groupie

*IMPROVED COMPUTER INDEPENDENCE Groupie

*ALL DOUBLE PRECISION Groupie

*ON SCREEN OUTPUT Groupie

*UNIFORM TREATMENT OF ENDF/B I/O Groupie

*IMPROVED OUTPUT PRECISION Groupie

*DEFINED SCRATCH FILE NAMES Groupie

*UP TO 1000 GROUP MULTI-BAND Groupie

CALCULATION (PREVIOUSLY 175) Groupie

*MAXIMUM NUMBER OF GROUPS REDUCED Groupie

FROM 3,000 TO 1,000 Groupie

*UP TO 1000 MATERIALS Groupie

(PREVIOUSLY 100) Groupie

*CORRECTED USE OF MAXWELLIAN + Groupie

1/E + FISSION SPECTRUM Groupie

*ONLY 2 BAND VERSION DISTRIBUTED Groupie

(CONTACT AUTHOR FOR DETAILS) Groupie

*DEFINED SCRATCH FILE NAMES Groupie

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Groupie

POINT READ FOR MORE DIGITS Groupie

*UPDATED TEST FOR ENDF/B FORMAT Groupie

VERSION BASED ON RECENT FORMAT CHANGE Groupie

*GENERAL IMPROVEMENTS BASED ON Groupie

USER FEEDBACK Groupie

VERSION 99-2 (JUNE 1999) *ASSUME ENDF/B-VI, NOT V, IF MISSING Groupie

MF=1, MT-451. Groupie

VERS. 2000-1 (FEBRUARY 2000)*ADDED MF=10, ACTIVATION CROSS SECTION Groupie

PROCESSING. Groupie

*GENERAL IMPROVEMENTS BASED ON Groupie

USER FEEDBACK Groupie

VERS. 2002-1 (FEBRUARY 2002)*ADDED TART 700 GROUP STRUCTURE Groupie

*ADDED VARIABLE SIGMA0 INPUT OPTION Groupie

(MAY 2002) *OPTIONAL INPUT PARAMETERS Groupie

(NOV. 2002) *ADDED SAND-II EXTENDED DOWN TO Groupie

1.0E-5 EV. Groupie

(JUNE 2003) *CORRECTED SAND-II 620 AND 640 GROUP Groupie

ENERGY BOUNDARIES DEFINITIONS. Groupie

VERS. 2004-1 (SEPT. 2004) *INCREASED PAGE SIZE FROM 30000 TO Groupie

120000 POINTS Groupie

*ADDED "OTHER" AS ADDITIONAL REACTION Groupie

TO IMPROVE MULTI-BAND FITTING Groupie

*ADDED ITERATION FOR "BEST" PARTIAL Groupie

PARAMETERS. Groupie

*DO NOT SKIP LOW TOTAL ENERGY RANGES Groupie

WHEN DEFINING AVERAGE CROSS SECTIONS - Groupie

THIS MAKES OUTPUT COMPATIBLE WITH Groupie

ANY STANDARD AVERAGING PROCEDURE Groupie

Groupie

OWNED, MAINTAINED AND DISTRIBUTED BY Groupie

------------------------------------ Groupie

THE NUCLEAR DATA SECTION Groupie

INTERNATIONAL ATOMIC ENERGY AGENCY Groupie

P.O. BOX 100 Groupie

A-1400, VIENNA, AUSTRIA Groupie

EUROPE Groupie

Groupie

ORIGINALLY WRITTEN BY Groupie

------------------------------------ Groupie

DERMOTT E. CULLEN Groupie

UNIVERSITY OF CALIFORNIA Groupie

LAWRENCE LIVERMORE NATIONAL LABORATORY Groupie

L-159 Groupie

P.O. BOX 808 Groupie

LIVERMORE, CA 94550 Groupie

U.S.A. Groupie

TELEPHONE 925-423-7359 Groupie

E. MAIL CULLEN1@LLNL.GOV Groupie

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Groupie

Groupie

AUTHORS MESSAGE Groupie

--------------- Groupie

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Groupie

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Groupie

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Groupie

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY Groupie

THE COMMENTS CONCERNING MACHINE DEPENDENT CODING. Groupie

Groupie

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Groupie

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Groupie

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Groupie

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Groupie

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Groupie

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Groupie

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Groupie

COMPUTER. Groupie

Groupie

PURPOSE Groupie

------- Groupie

THIS PROGRAM IS DESIGNED TO CALCULATE ANY COMBINATION OF Groupie

THE FOLLOWING QUANTITIES FROM LINEARLY INTERPOLABLE TABULATED Groupie

CROSS SECTIONS IN THE ENDF/B FORMAT Groupie

Groupie

(1) UNSHIELDED GROUP AVERAGED CROSS SECTIONS Groupie

(2) BONDARENKO SELF-SHIELDED GROUP AVERAGED CROSS SECTIONS Groupie

(3) MULTI-BAND PARAMETERS Groupie

Groupie

IN THE FOLLOWING FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B Groupie

TAPE--WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS, Groupie

DISK OR ANY OTHER MEDIUM. Groupie

Groupie

ENDF/B FORMAT Groupie

------------- Groupie

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Groupie

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Groupie

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV OR V FORMAT). Groupie

Groupie

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Groupie

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Groupie

ASSUMED THAT THE MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE Groupie

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Groupie

CORRECTLY OUTPUT ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451 Groupie

AND ALL SECTIONS OF MF= 3 MUST BE CORRECT. THE PROGRAM COPIES ALL Groupie

OTHER SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO Groupie

THE CORRECTNESS OR INCORRECTNESS OF ALL OTHER SECTIONS. Groupie

Groupie

ALL FILE 3 CROSS SECTIONS THAT ARE USED BY THIS PROGRAM MUST BE Groupie

LINEARLY INTERPOLABLE IN ENERGY AND CROSS SECTION (ENDF/B Groupie

INTERPOLATION LAW 2). FILE 3 BACKGROUND CROSS SECTIONS MAY BE MADE Groupie

LINEARLY INTERPOLABLE USING PROGRAM LINEAR (UCRL-50400, VOL. 17, Groupie

PART A). THE RESONANCE CONTRIBUTION MAY BE ADDED TO THE BACKGROUND Groupie

CROSS SECTIONS USING PROGRAM RECENT (UCRL-50400, VOL. 17, PART B). Groupie

IF THIS PROGRAM FINDS THAT THE FILE 3 CROSS SECTIONS ARE NOT Groupie

LINEARLY INTERPOLABLE THIS PROGRAM WILL TERMINATE EXECUTION. Groupie

Groupie

CONTENTS OF OUTPUT Groupie

------------------ Groupie

IF ENDF/B FORMATTED OUTPUT IS REQUESTED ENTIRE EVALUATIONS ARE Groupie

OUTPUT, NOT JUST THE MULTI-GROUPED FILE 3 CROSS SECTIONS, E.G. Groupie

ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO INCLUDED. Groupie

Groupie

DOCUMENTATION Groupie

------------- Groupie

THE FACT THAT THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED Groupie

BY THE ADDITION OF THREE COMMENT CARDS AT THE END OF EACH Groupie

HOLLERITH SECTION TO DESCRIBE THE GROUP STRUCTURE AND WEIGHTING Groupie

SPECTRUM, E.G. Groupie

Groupie

********************** PROGRAM GROUPIE (2004-1) *************** Groupie

UNSHIELDED GROUP AVERAGES USING 69 GROUPS (WIMS) Groupie

MAXWELLIAN, 1/E AND FISSION WEIGHTING SPECTRUM Groupie

Groupie

THE ORDER OF ALL SIMILAR COMMENTS (FROM LINEAR, RECENT AND SIGMA1) Groupie

REPRESENTS A COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON Groupie

THE DATA. Groupie

Groupie

THESE COMMENT CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Groupie

I.E., THIS PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Groupie

OF THE HOLLERITH SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF Groupie

EARLIER VERSIONS OF ENDF/B. BY READING AN EXISTING MF=1, MT=451 Groupie

IT IS POSSIBLE FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF Groupie

THE ENDF/B FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF Groupie

MF=1, MT=451 PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO Groupie

DETERMINE WHICH VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND Groupie

AS SUCH IT IS IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT Groupie

SHOULD BE USED TO CREATE A HOLLERITH SECTION. Groupie

Groupie

REACTION INDEX Groupie

-------------- Groupie

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Groupie

SECTION MF=1, MT=451 OF EACH EVALUATION. Groupie

Groupie

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Groupie

THIS CONVENTION HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT Groupie

REQUIRE A CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Groupie

NOT CONSIDERED WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING Groupie

A CORRECT REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE Groupie

A REACTION INDEX FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Groupie

YOU MAY USE PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX. Groupie

Groupie

SECTION SIZE Groupie

------------ Groupie

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Groupie

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Groupie

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Groupie

Groupie

SELECTION OF DATA Groupie

----------------- Groupie

THE PROGRAM SELECTS MATERIALS TO BE PROCESSED BASED EITHER ON Groupie

MAT (ENDF/B MAT NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR Groupie

ZA RANGES TO BE SPECIFIED. THE PROGRAM WILL ASSUME THAT THE Groupie

ENDF/B TAPE IS IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS Groupie

USED TO SELECT MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA Groupie

IS FOUND THAT IS ABOVE THE RANGE OF ALL REQUESTS. Groupie

Groupie

ENERGY ORDER AND UNITS Groupie

---------------------- Groupie

ALL ENERGIES (FOR CROSS SECTIONS, WEIGHTING SPECTRUM OR GROUP Groupie

BOUNDARIES) MUST BE IN UNITS OF EV AND MUST BE IN ASCENDING Groupie

NUMERICAL ORDER. Groupie

Groupie

ENERGY GRID Groupie

----------- Groupie

ALTHOUGH ALL REACTIONS MUST TO LINEARLY INTERPOLABLE, THEY DO NOT Groupie

ALL HAVE TO USE THE SAME ENERGY GRID. EACH REACTION CAN BE GIVEN Groupie

BY AN INDEPENDENT ENERGY GRID. THIS PROGRAM WILL PROCEED FROM Groupie

THE LOWEST TO HIGHEST ENERGY SELECTING EACH ENERGY INTERVAL OVER Groupie

WHICH ALL DATA, FOR ANY GIVEN CALCULATION, ARE ALL LINEARLY Groupie

INTERPOLABLE. Groupie

Groupie

GROUP STRUCTURE Groupie

--------------- Groupie

THIS PROGRAM IS DESIGNED TO USE AN ARBITRARY ENERGY GROUP Groupie

STRUCTURE WHERE THE ENERGIES ARE IN EV AND ARE IN INCREASING Groupie

ENERGY ORDER. THE MAXIMUM NUMBER OF GROUPS IS 1000. Groupie

Groupie

THE USER MAY INPUT AN ARBITRARY GROUP STRUCTURE OR THE USER MAY Groupie

USE USE ONE OF THE SEVEN BUILT-IN GROUP STRUCTURES. Groupie

(0) 175 GROUP (TART STRUCTURE) Groupie

(1) 50 GROUP (ORNL STRUCTURE) Groupie

(2) 126 GROUP (ORNL STRUCTURE) Groupie

(3) 171 GROUP (ORNL STRUCTURE) Groupie

(4) 620 GROUP (SAND-II STRUCTURE, UP TO 18 MEV) Groupie

(5) 640 GROUP (SAND-II STRUCTURE, UP TO 20 MEV) Groupie

(6) 69 GROUP (WIMS STRUCTURE) Groupie

(7) 68 GROUP (GAM-I STRUCTURE) Groupie

(8) 99 GROUP (GAM-II STRUCTURE) Groupie

(9) 54 GROUP (MUFT STRUCTURE) Groupie

(10) 28 GROUP (ABBN STRUCTURE) Groupie

(11) 650 GROUP (TART STRUCTURE) Groupie

(12) 700 GROUP (TART STRUCTURE) Groupie

(13) 665 GROUP (SAND-II STRUCTURE, 1.0e-5 eV, UP TO 18 MEV) Groupie

(14) 685 GROUP (SAND-II STRUCTURE, 1.0e-5 eV, UP TO 20 MEV) Groupie

Groupie

GROUP AVERAGES Groupie

-------------- Groupie

THIS PROGRAM DEFINES GROUP AVERAGED CROSS SECTIONS AS... Groupie

Groupie

(INTEGRAL E1 TO E2) (SIGMA(E)*S(E)*WT(E)*DE) Groupie

AVERAGE = ----------------------------------------- Groupie

(INTEGRAL E1 TO E2) (S(E)*WT(E)*DE) Groupie

WHERE... Groupie

Groupie

AVERAGE = GROUP AVERAGED CROSS SECTION Groupie

E1, E2 = ENERGY LIMITS OF THE GROUP Groupie

SIGMA(E) = ENERGY DEPENDENT CROSS SECTION FOR ANY GIVEN REACTION Groupie

S(E) = ENERGY DEPENDENT WEIGHTING SPECTRUM Groupie

WT(E) = ENERGY DEPENDENT SELF-SHIELDING FACTOR. Groupie

Groupie

ENERGY DEPENDENT WEIGHTING SPECTRUM Groupie

----------------------------------- Groupie

THE ENERGY DEPENDENT WEIGHTING SPECTRUM IS GIVEN BY AN ARBITRARY Groupie

TABULATED LINERLY INTERPOLABLE FUNCTION WHICH CAN BE DESCRIBED Groupie

BY AN ARBITRARY NUMBER OF POINTS. THIS ALLOWS THE USER TO Groupie

SPECIFY ANY DESIRED WEIGHTING SPECTRUM TO ANY GIVEN DEGREE OF Groupie

ACCURACY. REMEMBER THAT THE PROGRAM WILL ASSUME THAT THE SPECTRUM Groupie

IS LINEARLY INTERPOLABLE BETWEEN TABULATED POINTS. THEREFORE THE Groupie

USER SHOULD USE ENOUGH POINTS TO INSURE AN ADEQUATE REPRESENTATION Groupie

OF THE SPECTRUM BETWEEN TABULATED DATA POINTS. Groupie

Groupie

THE PRESENT VERSION OF THE CODE HAS THREE BULIT-IN WEIGHTING Groupie

SPECTRA, Groupie

Groupie

(1) CONSTANT Groupie

(2) 1/E Groupie

(3) MAXWELLIAN = E*EXP(-E/KT)/KT (0.0 TO 4*KT) Groupie

1/E = C1/E (4*KT TO 67 KEV) Groupie

FISSION = C2*EXP(-E/WA)*SINH(SQRT(E*WB)) (ABOVE 67 KEV) Groupie

Groupie

KT = 0.253 EV (293 KELVIN) Groupie

WA = 9.65E+5 Groupie

WB = 2.29E-6 Groupie

C1, C2 = DEFINED TO MAKE SPECTRUM CONTINUOUS Groupie

Groupie

FISSION SPECTRUM CONSTANTS FROM Groupie

A.F.HENRY, NUCLEAR REACTOR ANALYSIS, P. 11, MIT PRESS (1975) Groupie

Groupie

UNSHIELDED GROUP AVERAGES Groupie

------------------------- Groupie

FOR UNSHIELDED AVERAGES THE SELF-SHIELDING FACTOR (WT(E)) IS SET Groupie

TO UNITY. THIS PROGRAM ALLOWS UP TO 1000 GROUPS. Groupie

Groupie

SELF-SHIELDED GROUP AVERAGES Groupie

---------------------------- Groupie

IF SELF-SHIELDED AVERAGES AND/OR MULTI-BAND PARAMETERS ARE Groupie

CALCULATED THIS PROGRAM ALLOWS UP TO 1000 GROUPS. SELF-SHIELDED Groupie

AVERAGES AND/OR MULTI-BAND PARAMETERS ARE CALCULATED FOR THE Groupie

TOTAL, ELASTIC, CAPTURE AND FISSION. Groupie

Groupie

FOR THE TOTAL, ELASTIC, CAPTURE AND FISSION THE PROGRAM USES A Groupie

WEIGHTING FUNCTION THAT IS A PRODUCT OF THE ENERGY DEPENDENT Groupie

WEIGHTING SPECTRUM TIMES A BONDERENKO TYPE SELF-SHIELDING FACTOR. Groupie

Groupie

WT(E) = S(E)/(TOTAL(E)+SIGMA0)**N Groupie

Groupie

WHERE... Groupie

Groupie

S(E) - ENERGY DEPENDENT WEIGHTING SPECTRUM (DEFINED BY Groupie

TABULATED VALUES AND LINEAR INTERPOLATION BETWEEN Groupie

TABULATED VALUES). Groupie

TOTAL(E) - ENERGY DEPENDENT TOTAL CROSS SECTION FOR ONE MATERIAL Groupie

(DEFINED BY TABULATED VALUES AND LINEAR INTERPOLATION Groupie

BETWEEN TABULATED VALUES). Groupie

SIGMA0 - CROSS SECTION TO REPRESENT THE EFFECT OF ALL OTHER Groupie

MATERIALS AND LEAKAGE (DEFINED WITHIN EACH GROUP TO BE Groupie

A MULTIPLE OF THE UNSHIELDED TOTAL CROSS SECTION WITHIN Groupie

THAT GROUP OR POWERS OF 10 - INPUT OPTION). Groupie

N - A POSITIVE INTEGER (0, 1, 2 OR 3). Groupie

Groupie

THE PROGRAM WILL USE ONE ENERGY DEPENDENT WEIGHTING SPECTRUM S(E) Groupie

AND 25 DIFFERENT BONDERENKO TYPE SELF-SHIELDING FACTORS (25 SIGMA0 Groupie

AND N COMBINATIONS) TO DEFINE 25 DIFFERENT AVERAGE CROSS SECTIONS, Groupie

FOR EACH REACTION, WITHIN EACH GROUP. Groupie

Groupie

THE 25 WEIGHTING FUNCTIONS USED ARE.... Groupie

(1) - UNSHIELDED CROSS SECTIONS (N=0) Groupie

(2-22)- PARTIALLY SHIELDED CROSS SECTIONS (N=1 ,VARIOUS SIGMA0) Groupie

THE VALUES OF SIGMA0 USED WILL BE EITHER, Groupie

(A) THE VALUES OF SIGMA0 THAT ARE USED VARY FROM 1024 Groupie

TIMES THE UNSHIELDED TOTAL CROSS SECTIONS IN STEPS OF 1/2 Groupie

DOWN TO 1/1024 TIMES THE UNSHIELDED TOTAL CROSS SECTION Groupie

(A RANGE OF OVER 1 MILLION, CENTERED ON THE UNSHIELDED Groupie

TOTAL CROSS SECTION WITHIN EACH GROUP). Groupie

(B) THE SAME CONSTANT VALUES OF SIGMA0 IN EACH GROUP. THE Groupie

VALUES OF SIGMA0 USED INCLUDE 40000, 20000, 10000, 7000, Groupie

4000, 2000, 1000, 700, 400, 200, 100, 70, 40, 20, 10, 7, Groupie

4, 2, 1, 0.7, 0.4 (A RANGE OF 100,000 SPANNING MORE THAN Groupie

THE RANGE OF SIGMA0 VALUES THAT MAY BE ENCOUNTERED IN Groupie

ACTUAL APPLICATIONS) Groupie

(23) - TOTALLY SHIELDED FLUX WEIGHTED CROSS SECTION Groupie

(N=1, SIGMA0=0) Groupie

(24) - TOTALLY SHIELDED CURRENT WEIGHTED CROSS SECTION Groupie

(N=2, SIGMA0=0) Groupie

(25) - TOTALLY SHIELDED COSINE SQUARED WEIGHTED CROSS SECTION Groupie

(N=3, SIGMA0=0) Groupie

Groupie

FOR ALL OTHER REACTIONS (EXCEPT TOTAL, ELASTIC, CAPTURE AND Groupie

FISSION) THE PROGRAM WILL USE THE ENERGY DEPENDENT WEIGHTING Groupie

SPECTRUM S(E) TO DEFINE THE UNSHIELDED (BONDERENKO N=0) Groupie

AVERAGED CROSS SECTION WITHIN EACH GROUP. Groupie

Groupie

CALCULATION OF RESONANCE INTEGRALS Groupie

---------------------------------- Groupie

IN A PURE ELASTIC ISOTROPICALLY SCATTERING MATERIAL WITH A Groupie

CONSTANT CROSS SECTION THE SPECTRUM WILL BE 1/E AND THERE WILL Groupie

BE NO SELF-SHIELDING. Groupie

Groupie

IN THIS CASE IF THE CROSS SECTION VARIES WITH ENERGY THE Groupie

SPECTRUM WILL STILL BE 1/E AND THE SELF-SHIELDING FACTOR WILL Groupie

BE EXACTLY 1/SIG-TOT(E) - WHERE SIG-TOT(E) = SIG-EL(E), SINCE Groupie

THERE IS ONLY SCATTERING. Groupie

Groupie

IF WE HAVE AN INFINITELY DILUTE AMOUNT OF A MATERIAL UNIFORMLY Groupie

MIXED WITH A PURE ELASTIC ISOTROPICALLY SCATTERING MATERIAL WITH Groupie

A CONSTANT CROSS SECTION THE STANDARD DEFINITION OF THE RESONANCE Groupie

INTEGRAL CAN BE USED TO DEFINE REACTION RATES FOR EACH REACTION. Groupie

Groupie

THE RESONANCE INTEGRAL IS DEFINED AS, Groupie

Groupie

RI = (INTEGRAL E1 TO E2) (SIGMA(E)*S(E)*WT(E)*DE) Groupie

Groupie

WHERE NORMALLY, Groupie

S(E) = 1/E Groupie

WT(E) = 1 - NO SELF-SHIELDING Groupie

Groupie

FROM THE ABOVE DEFINITION OF GROUP AVERAGED CROSS SECTIONS THE Groupie

RESONANCE INTEGRAL IS, Groupie

Groupie

RI = AVERAGE * (INTEGRAL E1 TO E2) (S(E)*WT(E)*DE) Groupie

Groupie

FOR A 1/E SPECTRUM AND NO SELF-SHIELDING THIS REDUCES TO, Groupie

Groupie

RI = AVERAGE* LOG(E2/E1) Groupie

Groupie

IN ANY OTHER SITUATION, INCLUDING ABSORPTION AND/OR ENERGY Groupie

DEPENDENT CROSS SECTIONS, THE SPECTRUM WILL NOT BE 1/E - Groupie

ABSORPTION WILL TEND TO DECREASE THE SPECTRUM PROGRESSIVELY Groupie

MORE AT LOWER ENERGIES - ENERGY DEPENDENCE OF THE CROSS SECTION Groupie

WILL LEAD TO SELF-SHIELDING. Groupie

Groupie

HERE WE WILL NOT ATTEMPT TO PERFORM A DETAILED SPECTRUM Groupie

CALCULATION TO ACCOUNT FOR ABSORPTION. Groupie

Groupie

HOWEVER, WE WILL EXTEND THE DEFINITION OF THE RESONANCE INTEGRAL Groupie

TO ACCOUNT FOR SELF-SHIELDING EFFECTS BY ALLOWING FOR INCLUSION Groupie

OF SELF-SHIELDING EFFECTS IN THE DEFINITION OF GROUP AVERAGES Groupie

AND THEN DEFINING THE RESONANCE INTEGRAL AS, Groupie

Groupie

RI = AVERAGE* LOG(E2/E1) Groupie

Groupie

IN ORDER TO CALCULATE RESONANCE INTEGRALS YOU MUST FOLLOW THESE Groupie

STEPS, Groupie

Groupie

1) SELECT A 1/E SPECTRUM - ON FIRST LINE OF INPUT PARAMETERS. Groupie

2) SELECT THE ENERGY BOUNDARIES - NORMALLY ONLY 1 GROUP FROM Groupie

0.5 EV UP TO 20 MEV - HOWEVER, YOU ARE FREE TO SELECT ANY Groupie

ENERGY RANGE THAT YOU WISH - YOU MAY EVEN SELECT MORE THAN Groupie

1 GROUP MERELY BY SPECIFYING MORE THAN 1 GROUP AS INPUT - Groupie

THIS CAN BE USED TO DEFINE THE CONTRIBUTIONS TO THE RESONANCE Groupie

INTEGRAL FROM INDIVIDUAL ENERGY RANGES. Groupie

3) SELECT THIS OPTION FOR THE UNSHIELDED AND/OR SHIELDED OUTPUT Groupie

LISTING - ON THE SECOND LINE OF INPUT PARAMETERS. Groupie

Groupie

WHEN THIS OPTION IS USED THE PROGRAM WILL CALCULATE GROUP AVERAGED Groupie

CROSS SECTIONS - AS DEFINED ABOVE - PRIOR TO OUTPUT THE RESULTS Groupie

WILL MERELY BE MULTIPLIED BY THE WIDTH OF THE GROUP ASSUMING YOU Groupie

HAVE SELECTED A 1/E SPECTRUM - THERE IS NO CHECK ON THIS - THE Groupie

PROGRAM MERELY MULTIPLIES THE GROUP AVERAGED CROSS SECTIONS BY, Groupie

Groupie

LOG(E2/E1) - WHERE E2 AND E1 ARE THE GROUP ENERGY BOUNDARIES. Groupie

Groupie

WARNING - IT IS UP TO YOU TO INSURE THAT YOU FOLLOW EXACTLY THE Groupie

STEPS OUTLINED ABOVE IF YOU WISH TO OBTAIN MEANINGFUL Groupie

RESULTS. Groupie

Groupie

NOTE - OUTPUT IN THE ENDF/B FORMAT IS ALWAYS GROUP AVERAGED CROSS Groupie

SECTIONS, REGARDLESS OF WHETHER YOU ASK FOR AVERAGED CROSS Groupie

SECTIONS OR RESONANCE INTEGRALS - THIS IS BECAUSE DATA IN Groupie

THE ENDF/B FORMAT IS EXPLICITLY DEFINED TO BE CROSS Groupie

SECTIONS. Groupie

Groupie

RESONANCE INTEGRAL OUTPUT CAN ONLY BE OBTAINED IN THE Groupie

LISTING FORMATS. Groupie

Groupie

MINIMUM TOTAL CROSS SECTION TREATMENT Groupie

------------------------------------- Groupie

SINCE THE BONDARENKO SELF-SHIELDING DEPENDS ON 1/TOTAL CROSS Groupie

SECTION, THE ALGORITHM WILL BECOME NUMERICALLY UNSTABLE IF THE Groupie

TOTAL CROSS SECTION IS NEGATIVE (AS OCCURS IN MANY ENDF/B Groupie

EVALUATIONS). IF THE TOTAL IS LESS THAN SOME MINIMUM ALLOWABLE Groupie

VALUE (DEFINE BY OKMIN, PRESENTLY 1 MILLI-BARN) AN ERROR MESSAGE Groupie

WILL BE PRINTED AND FOR THE SELF-SHIELDING CALCULATION ALL ENERGY Groupie

INTERVALS IN WHICH THE TOTAL IS LESS THAN THE MINIMUM WILL BE Groupie

IGNORED. Groupie

Groupie

NOTE, FOR THE UNSHIELDED CALCULATIONS ALL CROSS SECTIONS WILL BE Groupie

CONSIDERED WHETHER THEY ARE POSITIVE OR NEGATIVE. THEREFORE IF Groupie

THE TOTAL CROSS SECTION IS NEGATIVE OR LESS THAN THE MINIMUM Groupie

VALUE THERE MAY BE AN INCONSISTENCY BETWEEN THE UNSHIELDED AND Groupie

THE SELF-SHIELDED CROSS SECTIONS. IF THE TOTAL CROSS SECTION IS Groupie

NEGATIVE AND SELF-SHIELDED CROSS SECTIONS ARE CALCULATED THE Groupie

PROGRAM WILL PRINT AN ERROR MESSAGE INDICATING THAT THE SELF- Groupie

SHIELDED RESULTS ARE UNRELIABLE AND SHOULD NOT BE USED. THEREFORE Groupie

IN THIS CASE THE PROGRAM WILL NOT ATTEMPT TO MODIFY THE UNSHIELDED Groupie

RESULTS TO ELIMINATE THE EFFECT OF NEGATIVE CROSS SECTIONS, SINCE Groupie

THE UNSHIELDED RESULTS ARE THE ONLY ONES WHICH TRULY REFLECT THE Groupie

ACTUAL INPUT. Groupie

Groupie

RESOLVED RESONANCE REGION Groupie

------------------------- Groupie

IN THE RESOLVED RESONANCE REGION (ACTUALLY EVERYWHERE BUT IN THE Groupie

UNRESOLVED RESONANCE REGION) THE CROSS SECTIONS OUTPUT BY LINEAR- Groupie

RECENT-SIGMA1 WILL BE ACTUAL ENERGY DEPENDENT CROSS SECTIONS AND Groupie

THE CALCULATIONS BY THIS PROGRAM WILL YIELD ACTUAL SHIELDED AND Groupie

UNSHIELDED CROSS SECTIONS. Groupie

Groupie

UNRESOLVED RESONANCE REGION Groupie

--------------------------- Groupie

IN THE UNRESOLVED RESONANCE REGION PROGRAM RECENT USES THE Groupie

UNRESOLVED RESONANCE PARAMETERS TO CALCULATE INFINITELY DILUTE Groupie

AVERAGE CROSS SECTIONS. THIS PROGRAM WILL MERELY READ THIS Groupie

INFINITELY DILUTE DATA AS IF IT WERE ENERGY DEPENDENT DATA AND Groupie

GROUP AVERAGE IT. AS SUCH THIS PROGRAM WILL PRODUCE THE CORRECT Groupie

UNSHIELDED CROSS SECTION IN THE UNRESOLVED RESONANCE REGION, BUT Groupie

IT WILL NOT PRODUCE THE CORRECT SELF-SHIELDING EFFECTS. Groupie

Groupie

ACCURACY OF RESULTS Groupie

------------------- Groupie

ALL INTEGRALS ARE PERFORMED ANALYTICALLY. THEREFORE NO ERROR IS Groupie

INTRODUCED DUE TO THE USE OF TRAPAZOIDAL OR OTHER INTEGRATION Groupie

SCHEME. THE TOTAL ERROR THAT CAN BE ASSIGNED TO THE RESULTING Groupie

AVERAGES IS JUST THAT DUE TO THE ERROR IN THE CROSS SECTIONS Groupie

AND ENERGY DEPENDENT WEIGHTING SPECTRUM. GENERALLY SINCE THE Groupie

THE ENERGY DEPENDENT WEIGHTING SPECTRUM APPEARS IN BOTH THE Groupie

NUMERATOR AND THE DENOMINATOR THE AVERAGES RAPIDLY BECOME Groupie

INSENSITIVE TO THE WEIGHTING SPECTRUM AS MORE GROUPS ARE USED. Groupie

SINCE THE WEIGHTING SPECTRUM IS LOADED IN THE PAGING SYSTEM THE Groupie

USER CAN DESCRIBE THE SPECTRUM TO ANY REQUIRED ACCURACY USING Groupie

ANY NUMBER OF ENERGY VS. SPECTRUM PAIRS. Groupie

Groupie

MULTI-BAND PARAMETERS Groupie

--------------------- Groupie

MULTI-BAND PARAMETERS ARE CALCULATED FOR THE TOTAL, ELASTIC, Groupie

CAPTURE AND FISSION REACTIONS. WITH THE NUMBER OF GROUPS THAT Groupie

ARE NORMALLY USED (SEE BUILT IN GROUP STRUCTURES) ALL OTHER Groupie

REACTIONS RESULT IN A NEGLIGABLE AMOUNT OF SELF-SHIELDING. AS Groupie

SUCH THEIR EQUIVALENT BAND CROSS SECTION WILL MERELY BE THEIR Groupie

UNSHIELDED VALUE WITHIN EACH BAND. Groupie

Groupie

FOR ANY GIVEN EVALUATION, WITHIN ANY GIVEN GROUP THIS PROGRAM Groupie

WILL GENERATE THE MINIMUM NUMBER OF BANDS REQUIRED WITHIN THAT Groupie

GROUP. AS OUTPUT TO THE COMPUTER READABLE DISK FILE THE BAND Groupie

PARAMETERS FOR EACH EVALUATION WILL BE FORMATTED TO HAVE THE Groupie

SAME NUMBER OF BANDS IN ALL GROUPS (WITH ZERO WEIGHT FOR SOME Groupie

BANDS WITHIN ANY GROUP). THE USER MAY DECIDE TO HAVE OUTPUT Groupie

EITHER WITH THE MINIMUM NUMBER OF BANDS REQUIRED FOR EACH Groupie

EVALUATION (E.G. 2 BANDS FOR HYDROGEN AND 4 BANDS FOR U-233) OR Groupie

THE SAME NUMBER OF BANDS FOR ALL EVALUATIONS (E.G. 4 BANDS FOR Groupie

BOTH HYDROGEN AND U-233). Groupie

Groupie

FOR 2 OR FEWER BANDS THE PROGRAM USES AN ANALYTIC EXPRESSION Groupie

TO DEFINE ALL MULTI-BAND PARAMETERS. FOR MORE THAN 2 BANDS THE Groupie

PROGRAM PERFORMS A NON-LINEAR FIT TO SELECT THE MULTI-BAND Groupie

PARAMETERS THAT MINIMIZE THE MAXIMUM FRACTIONAL ERROR AT ANY Groupie

POINT ALONG THE ENTIRE SELF-SHIELDING CURVE. THE NUMBER OF BANDS Groupie

REQUIRED WITHIN ANY GIVEN GROUP IS DEFINED BY INSURING THAT THE Groupie

MULTI-BAND PARAMETERS CAN BE USED TO ACCURATELY DEFINE SELF- Groupie

SHIELDED CROSS SECTIONS ALONG THE ENTIRE SELF-SHIELDING CURVE Groupie

FROM SIGMA0 = 0 TO INFINITY. THE USER MAY DEFINE THE ACCURACY Groupie

REQUIRED. Groupie

Groupie

ENDF/B FORMATTED UNSHIELDED AVERAGES Groupie

------------------------------------ Groupie

UNSHIELDED MULTI-GROUP AVERAGED CROSS SECTIONS FOR ALL REACTIONS Groupie

MAY BE OBTAINED IN THE ENDF/B FORTRAN IN EITHER HISTOGRAM Groupie

(INTERPOLATION LAW 1) OR LINEARLY INTERPOLABLE (INTERPOLATION Groupie

LAW 2) FORM. SEE INPUT BELOW FOR DETAILS. Groupie

Groupie

MIXTURES OF MATERIALS AND RESONANCE OVERLAP Groupie

------------------------------------------- Groupie

THE SELF-SHIELDED CROSS SECTIONS FOR THE INDIVIDUAL CONSTITUENTS Groupie

OF ANY MIXTURE CAN BE CALCULATED BY THIS PROGRAM BY REALIZING THAT Groupie

THIS PROGRAM ESSENTIALLY ONLY USES THE TOTAL CROSS SECTION AS A Groupie

WEIGHTING FUNCTION TO ACCOUNT FOR SELF-SHIELDING EFFECTS. FOR A Groupie

MIXTURE IT IS THEREFORE ONLY NECESSARY TO USE THE TOTAL CROSS Groupie

SECTION FOR THE MIXTURE IN PLACE OF THE ACTUAL TOTAL CROSS SECTION Groupie

FOR EACH CONSTITUENT AND TO RUN THIS PROGRAM. THIS CAN BE DONE BY Groupie

FIRST RUNNING PROGRAM MIXER TO CALCULATE THE ENERGY DEPENDENT Groupie

TOTAL CROSS SECTION FOR ANY COMPOSITE MIXTURE. NEXT, SUBSTITUTE Groupie

THIS COMPOSITE TOTAL CROSS SECTION FOR THE ACTUAL TOTAL CROSS Groupie

SECTION OF EACH CONSTITUENT (IN EACH ENDF/B FORMATTED EVALUATION). Groupie

FINALLY, RUN THIS PROGRAM TO CALCULATE THE SELF-SHIELDED CROSS Groupie

SECTION FOR EACH CONSTITUENT, PROPERLY ACCOUNTING FOR RESONANCE Groupie

OVERLAP BETWEEN THE RESONANCES OF ALL OF THE CONSTITUENTS OF THE Groupie

MIXTURE. DURING THE SAME RUN THESE SELF-SHIELDED CROSS SECTIONS Groupie

CAN IN TURN BE USED TO CALCULATE FULLY CORRELATED MULT-BAND Groupie

Groupie

MULTI-BAND PARAMETER OUTPUT FORMAT Groupie

---------------------------------- Groupie

FOR VERSIONS 92-2 AND LATER VERSIONS THE MULTI-BAND PARAMETERS Groupie

ARE OUTPUT IN A SIMPLE CHARACTER FORMAT, THAT CAN BE TRANSFERRED Groupie

AND USED ON VIRTUALLY ANY COMPUTER. Groupie

Groupie

THE BINARY FORMAT USED IN EARLIER VERSIONS OF THIS CODE IS NO Groupie

LONGER USED. Groupie

Groupie

CONTACT THE AUTHOR IF YOU WOULD LIKE TO RECEIVE A SIMPLE PROGRAM Groupie

TO READ THE CHARACTER FORMATTED MULTI-BAND PARAMETER FILE AND Groupie

CREATE A BINARY, RANDOM ACCESS FILE FOR USE ON VIRTUALLY ANY Groupie

COMPUTER. Groupie

Groupie

THE FORMAT OF THE CHARACTER FILE IS, Groupie

Groupie

RECORD COLUMNS FORMAT DESCRIPTION Groupie

1 1-72 18A4 LIBRARY DESCRIPTION (AS READ) Groupie

2 1-11 I11 MATERIAL ZA Groupie

12-22 I11 NUMBER GROUPS Groupie

23-33 I11 NUMBER OF BANDS Groupie

34-44 D11.4 TEMPERATURE (KELVIN) Groupie

45-55 1X,10A1 HOLLERITH DESCRIPTION OF ZA Groupie

3 1-11 D11.4 ENERGY (EV) - GROUP BOUNDARY. Groupie

12-22 D11.4 TOTAL (FIRST BAND) Groupie

23-33 D11.4 ELASTIC Groupie

34-44 D11.4 CAPTURE Groupie

35-55 D11.4 FISSION Groupie

4 1-11 ----- BLANK Groupie

12-22 D11.4 TOTAL (SECOND BAND) Groupie

23-33 D11.4 ELASTIC Groupie

34-44 D11.4 CAPTURE Groupie

35-55 D11.4 FISSION Groupie

Groupie

LINES 3 AND 4 ARE REPEATED FOR EACH GROUP. THE LAST LINE FOR EACH Groupie

MATERIAL (ZA) IS, Groupie

Groupie

N 1-11 D11.4 ENERGY (EV) - UPPER ENERGY LIMIT OF Groupie

LAST GROUP. Groupie

Groupie

FOR EXAMPLE, A 175 GROUP, 2 BAND FILE, FOR EACH MATERIAL WILL Groupie

CONTAIN 352 LINES = 1 HEADER LINE, 175 * 2 LINES OF PARAMETERS, Groupie

AND 1 FINAL LINE WITH THE UPPER ENERGY LIMIT Groupie

OF THE LAST GROUP. Groupie

Groupie

INPUT FILES Groupie

----------- Groupie

UNIT DESCRIPTION Groupie

---- ----------- Groupie

2 INPUT DATA (BCD - 80 CHARACTERS/RECORD) Groupie

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Groupie

Groupie

OUTPUT FILES Groupie

------------ Groupie

UNIT DESCRIPTION Groupie

---- ----------- Groupie

31 MULTI-BAND PARAMETERS CHARACTER FILE - OPTIONAL Groupie

(BCD - 80 CHARACTERS/RECORD) Groupie

32 SELF-SHIELDED CROSS SECTION LISTING - OPTIONAL Groupie

(BCD - 120 CHARACTERS/RECORD) Groupie

33 MULTI-BAND PARAMETER LISTING - OPTIONAL Groupie

(BCD - 120 CHARACTERS/RECORD) Groupie

34 UNSHIELDED CROSS SECTION LISTING - OPTION Groupie

(BCD - 120 CHARACTERS/RECORD) Groupie

3 OUTPUT REPORT (BCD - 80 CHARACTERS/RECORD) Groupie

11 MULTI-GROUP ENDF/B DATA - OPTIONAL Groupie

(BCD - 80 CHARACTERS/RECORD) Groupie

Groupie

SCRATCH FILES Groupie

------------- Groupie

UNIT FILENAME DESCRIPTION Groupie

---- -------- ----------- Groupie

8 ENERGY DEPENDENT WEIGHTING SPECTRUM Groupie

(BINARY - 40080 WORDS/BLOCK) Groupie

9 TOTAL CROSS SECTION Groupie

(BINARY - 40080 WORDS/BLOCK) Groupie

12 ELASTIC CROSS SECTION - ONLY FOR SELF-SHIELDING CALCULATION Groupie

(BINARY - 40080 WORDS/BLOCK) Groupie

13 CAPTURE CROSS SECTION - ONLY FOR SELF-SHIELDING CALCULATION Groupie

(BINARY - 40080 WORDS/BLOCK) Groupie

14 FISSION CROSS SECTION - ONLY FOR SELF-SHIELDING CALCULATION Groupie

(BINARY - 40080 WORDS/BLOCK) Groupie

Groupie

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2) Groupie

---------------------------------------------------------------- Groupie

UNIT FILE NAME Groupie

---- ---------- Groupie

2 GROUPIE.INP Groupie

3 GROUPIE.LST Groupie

8 (SCRATCH) Groupie

9 (SCRATCH) Groupie

10 ENDFB.IN Groupie

11 ENDFB.OUT Groupie

12 (SCRATCH) Groupie

13 (SCRATCH) Groupie

14 (SCRATCH) Groupie

31 MULTBAND.TAB Groupie

32 SHIELD.LST Groupie

33 MULTBAND.LST Groupie

34 UNSHIELD.LST Groupie

Groupie

I/O UNITS USED Groupie

-------------- Groupie

UNITS 2, 3 8, 9 AND 10 WILL ALWAYS BE USED. Groupie

UNITS 31 THROUGH 34 AND 11 ARE OPTIONALLY USED DEPENDING ON THE Groupie

OUTPUT REQUESTED. Groupie

UNITS 12, 13 AND 14 WILL ONLY BE USED IF SELF-SHIELDED OR Groupie

MULTIBAND OUTPUT IS REQUESTED. Groupie

Groupie

INPUT CARDS Groupie

----------- Groupie

CARD COLS. FORMAT DESCRIPTION Groupie

---- ----- ------ ----------- Groupie

1 1-11 I11 SELECTION CRITERIA (0=MAT, 1=ZA) Groupie

1 12-22 I11 NUMBER OF GROUPS. Groupie

=.GT.0 - ARBITRARY GROUP BOUNDARIES ARE READ Groupie

FROM INPUT FILE (N GROUPS REQUIRE Groupie

N+1 GROUP BOUNDARIES). CURRENT Groupie

PROGRAM MAXIMUM IS 1000 GROUPS. Groupie

BUILT-IN OPTIONS INCLUDE.... Groupie

= 0 - TART 175 GROUPS Groupie

= -1 - ORNL 50 GROUPS Groupie

= -2 - ORNL 126 GROUPS Groupie

= -3 - ORNL 171 GROUPS Groupie

= -4 - SAND-II 620 (665) GROUPS TO 18 MEV Groupie

= -5 - SAND-II 640 (685) GROUPS TO 20 MEV Groupie

= -6 - WIMS 69 GROUPS Groupie

= -7 - GAM-I 68 GROUPS Groupie

= -8 - GAM-II 99 GROUPS Groupie

= -9 - MUFT 54 GROUPS Groupie

=-10 - ABBN 28 GROUPS Groupie

=-11 - TART 650 GROUPS Groupie

=-12 - TART 700 GROUPS Groupie

=-13 - SAND-II 665 GROUPS TO 18 MEV Groupie

=-14 - SAND-II 685 GROUPS TO 20 MEV Groupie

1 23-33 I11 MULTI-BAND SELECTOR Groupie

= 0 - NO MULTI-BAND CALCULATIONS Groupie

= 1 - 2 BAND. CONSERVE AV(TOT), AV(1/TOT) Groupie

AND AV(1/TOT**2) Groupie

= 2 - 2 BAND. CONSERVE AV(TOT), AV(1/TOT) Groupie

AND AV(1/(TOT+SIGMA0)) WHERE Groupie

SIGMA0 = AV(TOT) IN EACH GROUP Groupie

= 3-5- MULTI-BAND FIT. CONSERVE AV(TOT) AND Groupie

MINIMIZE FRACTIONAL ERROR FOR ENTIRE Groupie

SELF-SHIELDING CURVE (SIGMA0 = 0 TO Groupie

INFINITY) Groupie

IF THE SELECTOR IS POSITIVE (1 TO 5) THE Groupie

MINIMUM NUMBER OF BANDS WILL BE OUTPUT FOR Groupie

EACH ISOTOPE INDEPENDENTLY. IF THE SELECTOR Groupie

IS NEGATIVE (-1 TO -5) THE SAME NUMBER OF Groupie

BANDS (ABS(SELECTOR)) WILL BE OUTPUT FOR Groupie

ALL ISOTOPES. Groupie

1 34-44 I11 NUMBER OF POINTS USED TO DESCRIBE ENERGY Groupie

DEPENDENT WEIGHTING SPECTRUM S(E). Groupie

= -2 - MAXWELLIAN - UP TO 0.1 EV Groupie

1/E - 0.1 EV TO 67 KEV Groupie

FISSION - ABOVE 67 KEV Groupie

= -1 - 1/E Groupie

= 0 OR 1- ENERGY INDEPENDENT (SO CALLED FLAT Groupie

WEIGHTING SPECTRUM). Groupie

= .GT.1 - READ THIS MANY POINTS FROM INPUT Groupie

TO DESCRIBE WEIGHTING SPECTRUM. Groupie

NO LIMIT TO THE NUMBER OF POINTS Groupie

USED TO DESCRIBE WEIGHTING. Groupie

1 45-55 D11.4 MULTI-BAND CONVERGENCE CRITERIA. Groupie

ONLY USED FOR 3 OR MORE BANDS. THE NUMBER OF Groupie

BANDS IN EACH GROUPS IS SELECTED TO INSURE Groupie

THAT THE ENTIRE SELF-SHIELDING CURVE CAN BE Groupie

REPRODUCED TO WITHIN THIS FRACTIONAL ERROR. Groupie

= .LT. 0.0001 - USE STANDARD 0.001 Groupie

(0.1 PER-CENT) Groupie

= .GE. 0.0001 - USE AS CONVERGENCE CRITERIA Groupie

1 56-66 I11 SIGMA-0 DEFINITION SELECTOR. Groupie

< 0 - 21 VALUES OF SIGMA0 ARE READ INPUT AND Groupie

INTERPRETED AS FIXED VALUES = SAME AS Groupie

= 1 DESCRIPTION BELOW Groupie

INPUT VALUES MUST ALL BE, Groupie

1) GREATER THAN 0 Groupie

2) IN DESCENDING VALUE ORDER Groupie

= 0 - SIGMA-0 WILL BE DEFINED AS A MULTIPLE Groupie

OF THE UNSHIELDED TOTAL CROSS SECTION Groupie

IN EACH GROUP (VALUES OF 1/1024 TO Groupie

1024 IN STEPS OF A FACTOR OF 2 WILL Groupie

BE USED AS THE MULTIPLIER). Groupie

= 1 - SIGMA-0 WILL BE DEFINED AS THE SAME Groupie

NUMBER OF BARNS IN EACH GROUP (VALUES Groupie

40000 TO 0.4 BARNS WILL BE USED. WITHIN Groupie

EACH DECADE VALUES OF 10, 7, 4, 2, 1 Groupie

BARNS WILL BE USED). Groupie

2-4 1-66 6D11.4 IF SIGMA-0 DEFINITION SELECTOR < 0, THE NEXT Groupie

4 LINES OF INPUT ARE THE 22 VALUES OF SIGMA0, Groupie

6 PER LINE. Groupie

2 1-60 A60 ENDF/B INPUT DATA FILENAME Groupie

(STANDARD OPTION = ENDFB.IN) Groupie

3 1-60 A60 ENDF/B OUTPUT DATA FILENAME Groupie

(STANDARD OPTION = ENDFB.OUT) Groupie

Groupie

THE FOURTH INPUT CARD IS USED TO SELECT ALL DESIRED OUTPUT MODES. Groupie

EACH OUTPUT DEVICE MAY BE TURNED OFF (0) OR ON (1). THEREFORE Groupie

THEREFORE EACH OF THE FOLLOWING INPUT PARAMETERS MAY BE EITHER Groupie

ZERO TO INDICATE NO OUTPUT OR NON-ZERO TO INDICATE OUTPUT. Groupie

Groupie

4 1-11 I11 SELF-SHIELDED CROSS SECTION LISTING Groupie

= 1 - CROSS SECTIONS Groupie

= 2 - RESONANCE INTEGRALS Groupie

4 12-22 I11 MULTI-BAND PARAMETER LISTING Groupie

4 23-33 I11 MULTI-BAND PARAMETERS COMPUTER READABLE Groupie

4 34-44 I11 UNSHIELDED CROSS SECTIONS IN ENDF/B FORMAT Groupie

= 1 - HISTOGRAM FORMAT (INTERPOLATION LAW 1) Groupie

= 2 - LINEAR-LINEAR (INTERPOLATION LAW 2) Groupie

4 45-55 I11 UNSHIELDED CROSS SECTIONS LISTING Groupie

= 1 - CROSS SECTIONS Groupie

= 2 - RESONANCE INTEGRALS Groupie

Groupie

5 1-80 18A4 LIBRARY IDENTIFICATION. ANY TEXT THAT THE Groupie

USER WISHES TO IDENTIFY THE MULTI-BAND Groupie

PARAMETERS. THIS LIBRARY IDENTIFICATION IS Groupie

WRITTEN INTO THE COMPUTER READABLE MULTI-BAND Groupie

DATA FILE. Groupie

Groupie

6-N 1- 6 I6 LOWER MAT OR ZA LIMIT Groupie

7- 8 I2 LOWER MF LIMIT Groupie

9-11 I3 LOWER MT LIMIT Groupie

12-17 I11 UPPER MAT OR ZA LIMIT Groupie

18-19 I2 UPPER MF LIMIT Groupie

20-22 I3 UPPER MT LIMIT Groupie

UP TO 100 RANGES MAY BE SPECIFIED, ONE RANGE Groupie

PER LINE. THE LIST OF RANGES IS TERMINATED Groupie

BY A BLANK CARD. IF THE UPPER MAT OR ZA Groupie

LIMIT IS LESS THAN THE LOWER LIMIT THE UPPER Groupie

IS SET EQUAL TO THE LOWER LIMIT. IF THE UPPER Groupie

MF OR MT LIMIT IS ZERO IT WILL BE SET EQUAL Groupie

TO ITS MAXIMUM VALUE, 99 OR 999, RESPECTIVELY Groupie

IF THE FIRST REQUEST LINE IS BLANK IT WILL Groupie

TERMINATE THE LIST OF REQUESTS AND CAUSE ALL Groupie

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT). Groupie

Groupie

VARY 1-66 6D11.4 ENERGY GROUP BOUNDARIES. ONLY REQUIRED IF Groupie

THE NUMBER OF GROUPS INDICATED ON THE FIRST Groupie

INPUT CARD IS POSITIVE. ALL ENERGIES MUST Groupie

BE IN ASCENDING ENERGY IN EV. THE PRESENT Groupie

LIMITS ARE 1 TO 1000 GROUPS. FOR N GROUPS Groupie

N+1 BOUNDARIES WILL BE READ FROM THE Groupie

INPUT FILE, E.G. IF THE FIRST INPUT CARD Groupie

INDICATES 20 GROUPS, 21 ENERGY BOUNDARIES Groupie

WILL BE READ FROM THE INPUT FILE. Groupie

Groupie

VARY 1-66 6D11.4 ENERGY DEPENDENT WEIGHTING SPECTRUM. ONLY Groupie

REQUIRED IF THE NUMBER OF POINTS INDICATED Groupie

ON FIRST CARD IS MORE THAN ONE. DATA IS Groupie

GIVEN IN (ENERGY, WEIGHT) PAIRS, UP TO 3 Groupie

PAIRS PER CARD, USING ANY NUMBER OF CARDS Groupie

REQUIRED. ENERGIES MUST BE IN ASCENDING Groupie

ORDER IN EV. THE SPECTRUM VALUES MUST BE Groupie

NON-NEGATIVE. THE ENERGY RANGE OF SPECTRUM Groupie

MUST AT LEAST SPAN THE ENERGY RANGE OF THE Groupie

ENERGY GROUPS. SINCE SPECTRUM IS STORED IN Groupie

PAGING SYSTEM THERE IS NO LIMIT TO NUMBER Groupie

OF POINTS THAT CAN BE USED TO DESCRIBE THE Groupie

WEIGHTING SPECTRUM. Groupie

Groupie

EXAMPLE INPUT NO. 1 Groupie

------------------- Groupie

REQUEST DATA BY MAT AND PROCESS ALL DATA (ALL MAT BETWEEN 1 AND Groupie

9999). USE THE TART 175 GROUP STRUCTURE, GENERATE 2 BAND Groupie

PARAMETERS (THE FOR ALL ISOTOPES) TO 0.1 PER-CENT ACCURACY Groupie

IN THE SELF-SHIELDING CURVE. OUTPUT ALL LISTING, COMPUTER Groupie

READABLE AND ENDF/B FORMAT GROUP AVERAGES. Groupie

Groupie

EXPLICITLY SPECIFY THE STANDARD FILENAMES. Groupie

Groupie

THE FOLLOWING 7 INPUT LINES ARE REQUIRED. Groupie

Groupie

0 0 -2 0 1.00000-03 0 Groupie

ENDFB.IN Groupie

ENDFB.OUT Groupie

1 1 1 1 1 Groupie

TART 175 GROUP, 2 BAND LIBRARY TO 0.1 PER-CENT ACCURACY Groupie

1 1 1 9999 0 0 Groupie

(BLANK CARD TERMINATES REQUEST LIST) Groupie

Groupie

EXAMPLE INPUT NO. 2 Groupie

------------------- Groupie

THE SAME EXAMPLE 1, AS ABOVE, ONLY THE ENDF/B DATA WILL BE READ Groupie

FROM \ENDFB6\SIGMA1\K300\ZA092238 (U-238 AT 300 KELVIN) AND Groupie

WRITTEN TO \ENDFB6\GROUPIE\K300\ZA092238 Groupie

Groupie

THE FOLLOWING 7 INPUT LINES ARE REQUIRED. Groupie

Groupie

0 0 -2 0 1.00000-03 0 Groupie

\ENDFB6\SIGMA1\K300\ZA092238 Groupie

\ENDFB6\GROUPIE\K300\ZA092238 Groupie

1 1 1 1 1 Groupie

TART 175 GROUP, 2 BAND LIBRARY TO 0.1 PER-CENT ACCURACY Groupie

1 1 1 9999 0 0 Groupie

(BLANK CARD TERMINATES REQUEST LIST) Groupie

Groupie

EXAMPLE INPUT NO. 3 Groupie

------------------- Groupie

PROCESS ALL DATA. USE 1/V WEIGHTING IN ORDER TO CALCULATE Groupie

UNSHIELDED ONE GROUP CROSS SECTIONS OVER THE ENERGY RANGE 0.5 EV Groupie

TO 1 MEV (NOTE THAT THE RESULTS ARE SIMPLY PROPORTIONAL TO THE Groupie

RESONANCE INTEGRAL FOR EACH REACTION). OUTPUT UNSHIELDED LISTING. Groupie

Groupie

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Groupie

THEN USE STANDARD FILENAMES. Groupie

Groupie

THE FOLLOWING 7 INPUT CARDS ARE REQUIRED. Groupie

Groupie

0 0 1 -1 0 Groupie

(USE STANDARD FILENAME = ENDFB.IN) Groupie

(USE STANDARD FILENAME = ENDFB.OUT) Groupie

0 0 0 0 1 Groupie

RESONANCE INTEGRAL CALCULATION (FROM 0.5 EV TO 1 MEV) Groupie

(RETRIEVE ALL DATA, TERMINATE REQUEST LIST) Groupie

5.00000-01 1.00000+06 Groupie

Groupie

======================================================================= Groupie

======================================================================= Legend

Legend

PROGRAM LEGEND Legend

VERSION 80-1 (SEPTEMBER 1980) Legend

VERSION 84-1 (NOVEMBER 1984) Legend

VERSION 86-1 (JANUARY 1986) *CORRECTED BASED ON USER COMMENTS Legend

*FORTRAN-77/H VERSION Legend

VERSION 87-1 (JANUARY 1987) *CORRECTED BASED ON USER COMMENTS Legend

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Legend

FILE NAMES (SEE, SUBROUTINE FILEIO Legend

FOR DETAILS). Legend

*IMPROVED BASED ON USER COMMENTS. Legend

VERSION 89-1 (JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO Legend

INSURE PROGRAM WILL NOT DO ANYTHING Legend

CRAZY. Legend

*UPDATED TO USE NEW PROGRAM CONVERT Legend

KEYWORDS. Legend

*ADDED LIVERMORE CIVIC COMPILER Legend

CONVENTIONS. Legend

VERSION 92-1 (JANUARY 1992) *FOR ANGULAR DISTRIBUTIONS CALCULATED Legend

FROM LEGENDRE COEFFICIENTS, INTERVAL Legend

HALF TO CONVERGENCE. Legend

*UPDATED BASED ON USER COMMENTS Legend

*ADDED FORTRAN SAVE OPTION Legend

*ADDED SELECTED OF DATA TO PROCESS Legend

BY MAT/MF/MT/ENERGY RANGES. Legend

*WARNING...THE INPUT PARAMETER FORMAT Legend

HAS BEEN CHANGED - FOR DETAILS SEE Legend

BELOW. Legend

VERSION 92-2 (SEPT. 1992) *CORRECTED PROCESSING OF ISOTROPIC Legend

ANGULAR DISTRIBUTIONS Legend

VERSION 94-1 (JANUARY 1994) *VARIABLE ENDF/B DATA FILENAMES Legend

TO ALLOW ACCESS TO FILE STRUCTURES Legend

(WARNING - INPUT PARAMETER FORMAT Legend

HAS BEEN CHANGED) Legend

*CLOSE ALL FILES BEFORE TERMINATING Legend

(SEE, SUBROUTINE ENDIT) Legend

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Legend

*IMPROVED COMPUTER INDEPENDENCE Legend

*ALL DOUBLE PRECISION Legend

*ON SCREEN OUTPUT Legend

*UNIFORM TREATMENT OF ENDF/B I/O Legend

*IMPROVED OUTPUT PRECISION Legend

*INCREASED MAX. POINTS FROM 5,000 Legend

TO 20,000. Legend

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Legend

POINT READ FOR MORE DIGITS Legend

*UPDATED TEST FOR ENDF/B FORMAT Legend

VERSION BASED ON RECENT FORMAT CHANGE Legend

*GENERAL IMPROVEMENTS BASED ON Legend

USER FEEDBACK Legend

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Legend

USER FEEDBACK Legend

VERS. 2001-1 (MARCH 2001) *UPDATED TO HANDLE COMBINATIONS OF Legend

LEGENDRE COEFFICIENTS AT LOW ENERGY Legend

AND TABULATED DATA AT HIGH ENERGY. Legend

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Legend

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Legend

Legend

OWNED, MAINTAINED AND DISTRIBUTED BY Legend

------------------------------------ Legend

THE NUCLEAR DATA SECTION Legend

INTERNATIONAL ATOMIC ENERGY AGENCY Legend

P.O. BOX 100 Legend

A-1400, VIENNA, AUSTRIA Legend

EUROPE Legend

Legend

ORIGINALLY WRITTEN BY Legend

------------------------------------ Legend

DERMOTT E. CULLEN Legend

CURRENT ADDRESS Legend

UNIVERSITY OF CALIFORNIA Legend

LAWRENCE LIVERMORE NATIONAL LABORATORY Legend

L-159 Legend

P.O. BOX 808 Legend

LIVERMORE, CA 94550 Legend

U.S.A. Legend

TELEPHONE 925-423-7359 Legend

E. MAIL CULLEN1@LLNL.GOV Legend

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Legend

Legend

PURPOSE Legend

------- Legend

CALCULATE LINEARLY INTERPOLABLE TABULATED ANGULAR DISTRIBUTIONS Legend

STARTING FROM DATA IN THE ENDF/B FORMAT. ANGULAR DISTRIBUTIONS Legend

MAY BE DESCRIBED IN THE ENDF/B FORMAT IN ONE OF THREE WAYS. Legend

FOR EACH OF THESE THREE FORMS THE USER MAY CHOOSE (SEE, INPUT Legend

OPTIONS) TO EITHER COPY EACH TYPE OF DATA OR TO PROCESS IT AT Legend

AS FOLLOWS, Legend

Legend

(1) ANGULAR DISTRIBUTION IS ISOTROPIC AT ALL ENERGIES (LTT=0) Legend

------------------------------------------------------------- Legend

IN THIS CASE THE INPUT DATA DOES NOT INCLUDE ANY ANGULAR Legend

DISTRIBUTIONS. A SECTION MERELY CONTAINS A FLAG TO INDICATE Legend

THE ANGULAR DISTRIBUTION IS ISOTROPIC AT ALL ENERGIES. IN THIS Legend

CASE THE SECTION IS OUTPUT IN EXACTLY THE SAME FORM IN WHICH IT Legend

WAS READ FROM THE INPUT. Legend

Legend

(2) ANGULAR DISTRIBUTIONS GIVEN BY LEGENDRE COEFFICIENTS (LTT=1) Legend

---------------------------------------------------------------- Legend

LEGENDRE COEFFICIENTS ARE GIVEN AT A SERIES OF ENERGIES. AN Legend

INTERPOLATION LAW IS GIVEN BETWEEN ENERGIES. THE INTERPOLATION Legend

LAW BETWEEN ENERGIES IS COPIED AS INPUT (I.E., NO ATTEMPT IS Legend

MADE TO LINEARIZE THE VARIATION WITH ENERGY). FOR EACH ENERGY AT Legend

WHICH LEGENDRE COEFFICIENTS ARE GIVEN A LINEARLY INTERPOLABLE Legend

ANGULAR DISITRIBUTION IS RECONSTRUCTED IN THE SYSTEM IN WHICH THE Legend

THE COEFFICIENTS ARE GIVEN (I.E., CM OR LAB - NO ATTEMPT IS MADE Legend

TO CONVERT FROM ONE SYSTEM TO THE OTHER). A MAXIMUM OF 50 LEGENDRE Legend

COEFFICIENTS IS ALLOWED. REGARDLESS OF THE NUMBER OF COEFFICIENTS Legend

INPUT THE PROGRAM WILL ONLY USE COEFFICIENTS UP TO THE LAST ORDER Legend

AT WHICH THE COEFFICIENTS ARE NON-ZERO (E.G. IF COEFFICIENTS P1 Legend

THROUGH P12 ARE READ, BUT P9=P10=P11=P12=0.0, THE PROGRAM WILL Legend

ONLY USE COEFFICIENTS UP TO P8). IF OVER 50 NON-ZERO COEFFICIENTS Legend

ARE READ ONLY THE FIRST 50 WILL BE USED. Legend

Legend

(2) ANGULAR DISTRIBUTIONS IS TABULATED (LTT=2) Legend

---------------------------------------------------------------- Legend

ANGULAR DISTRIBUTIONS ARE GIVEN AT A SERIES OF ENERGIES. AN Legend

INTERPOLATION LAW IS GIVEN BETWEEN ENERGIES AND A SECOND Legend

INTERPOLATION LAW IS GIVEN AT EACH ENERGY TO INTERPOLATE BETWEEN Legend

THE POINTS IN EACH TABULATED DISTRIBUTION. AT EACH ENERGY THE Legend

ANGULAR DISTRIBUTION WILL BE CONVERTED TO LINEARLY INTERPOLABLE Legend

FORM. THE INTERPOLATION BETWEEN ENERGIES IS OUTPUT EXACTLY AS Legend

INPUT. THE INTERPOLATION LAW AT EACH ENERGY IS OUTPUT TO INDICATE Legend

THE NOW LINEARLY INTERPOLABLE ANGULAR DISTRIBUTION. Legend

Legend

(3) LEGENDRE COEFFICIENTS AND TABULATED (LTT=3) Legend

---------------------------------------------------------------- Legend

ENDF-102 SAYS THIS SHOULD BE LTT=4, BUT ALL OF THE EVALUATIONS Legend

IN ENDF/B-VI, RELEASE 7, USE LTT=3? THIS CODE WILL TREAT THESE Legend

AS LTT=4 - SEE BELOW. Legend

Legend

(4) LEGENDRE COEFFICIENTS AND TABULATED (LTT=4) Legend

---------------------------------------------------------------- Legend

THIS IS A COMBINATION OF (1) AND (2) DESCRIBED ABOVE. THE Legend

LEGENDRE DATA IS ALWAYS GIVEN FIRST, FOR LOWER ENERGIES, Legend

FOLLOWED BY TABULATED ANGULAR DISTRIBUTIONS, FOR HIGHER ENERGIES. Legend

Legend

THIS TYPE OF DATA CAN ONLY BE COPIED OR ALL CONVERTED TO Legend

TABULATED (LTT=2). Legend

Legend

POINT VALUES - NORMALIZED VS. UNNORMALIZED Legend

------------------------------------------------------------------ Legend

THE VALUE OF AN ANGULAR DISTRIBUTION AT ANY COSINE WILL BE Legend

CORRECTLY CALCULATED BY THIS CODE, BASED EITHER DIRECTLY ON THE Legend

ANGULAR DISTRIBUTION, OR ON THE SUM OF THE CONTRIBUTING LEGENDRE Legend

MOMENTS. Legend

Legend

ENDF/B ANGULAR DISTRIBUTIONS ARE BY DEFINITION NORMALIZED WHEN Legend

INTEGRATED OVER COSINE. THEREFORE THIS CODE WILL NORMALIZE EACH Legend

ANGULAR DISTRIBUTION BEFORE IT IS OUTPUT. THE OUTPUT REPORT FROM Legend

THIS CODE WILL INDICATE THE NORMALIZATION FACTOR USED. Legend

Legend

THE REASON THAT AN ANGULAR DISTRIBUTION MAY NOT BE NORMALIZED IS Legend

DUE TO THE APPROXIMATION OF CREATING LINEARLY INTERPOLABLE Legend

TABULATED ANGULAR DISTRIBUTIONS - THE MORE ACCURATELY THIS IS Legend

DONE THE CLOSER THE NORMALIZATION FACTOR WILL BE TO UNITY. AS YOU Legend

DECREASE THE ALLOWABLE ERROR THE NORMALIZED VALUES WILL APPROACH Legend

THE CORRECT POINT VALUES CALCULATED BY THE CODE. Legend

Legend

SINCE THE DATA IS NORMALIZED PRIOR TO OUTPUT THE RESULTS IN THE Legend

ENDF/B FORMAT MAY DIFFER SLIGHTLY FROM VALUES REFERRED TO BE ERROR Legend

MESSAGES, ETC. PRINTED BY THE CODE DURING EXECUTION. IN ALL CASES Legend

THE VALUES PRINTED BY THE CODE IN ERROR MESSAGES, ETC. SHOULD BE Legend

CONSIDERED TO BE THE CORRECT VALUES AND THE OUTPUT TABULATED Legend

ANGULAR DISTRIBUTIONS APPROXIMATE DUE TO THE RE-NORMALIZATION - Legend

TO RE-ITERATE, THE OUTPUT TABULATED VALUES ARE APPROXIMATE DUE Legend

TO THE APPROXIMATIONS USED IN CONSTRUCTING LINEAR INTERPOLABLE Legend

ANGULAR DISTRIBUTIONS TO WITHIN SOME ALLOWABLE TOLERANCE. Legend

Legend

ELIMINATION OF NEGATIVE VALUES Legend

------------------------------ Legend

THE RECONSTRUCTED ANGULAR DISTRIBUTION WILL BE TESTED AND IF IT Legend

IS NEGATIVE AT ONE OR MORE COSINES AN ERROR MESSAGE WILL BE OUTPUT Legend

AND BASED ON THE INPUT OPTION SELECTED ONE OF THE FOLLOWING Legend

CORRECTIVE ACTIONS WILL BE TAKEN (SEE, INPUT OPTIONS), Legend

(1) NO CORRECTION Legend

(2) CHANGE INDIVIDUAL LEGENDRE COEFFICIENTS (EACH BY LESS THAN Legend

1.0 PER-CENT) UNTIL THE RECONSTRUCTED ANGULAR DISTRIBUTION Legend

IS POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). THE ALLOWABLE Legend

PER-CENT CHANGE IN COEFFICIENTS AND MINIMUM CROSS SECTION CAN Legend

BE CHANGED BY INPUT. Legend

(3) CHANGE ALL LEGENDRE COEFFICIENTS TO FORCE DISTRIBUTION TO BE Legend

POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). WITH THIS OPTION Legend

THERE IS NO RESTRICTION ON THE AMOUNT THAT EACH COEFFICIENT Legend

IS CHANGED AND AS SUCH THIS OPTION SHOULD BE USED WITH Legend

CAUTION AND ONLY AS A LAST RESORT IF NO OTHER APPROACH CAN Legend

BE USED TO MAKE THE DISTRIBUTION POSITIVE. Legend

Legend

OUTPUT Legend

------ Legend

THE USER MAY REQUEST OUTPUT OF EITHER, Legend

(1) TABULATED VALUES - POSSIBLY CORRECTED TO ELIMINATE NEGATIVE Legend

VALUES. THE TABULATED DISTRIBUTION WILL BE NORMALIZED BEFORE Legend

OUTPUT. Legend

(2) LEGENDRE COEFFICIENTS - POSSIBLY CORRECTED TO ELIMINATE Legend

NEGATIVE VALUES AND WITHOUT HIGHER ORDER ZERO COEFFICIENTS. Legend

BY DEFINITION DISTRIBUTIONS DEFINED BY LEGENDRE COEFFICIENTS Legend

ARE NORMALIZED TO UNITY. Legend

Legend

(3) ANGULAR DISTRIBUTIONS GIVEN BY A TABULATION (LTT=2) Legend

------------------------------------------------------- Legend

TABULATED ANGULAR DISTRIBUTIONS ARE GIVEN AT A SERIES OF ENERGIES. Legend

AN INTERPOLATION LAW IS GIVEN BETWEEN ENERGIES. THE INTERPOLATION Legend

LAW BETWEEN ENERGIES IS COPIED AS INPUT (I.E., NO ATTEMPT IS Legend

MADE TO LINEARIZE THE VARIATION WITH ENERGY). FOR EACH ENERGY AT Legend

AT WHICH TABULATED DATA ARE GIVEN A LINEARLY INTERPOLABLE ANGULAR Legend

DISTRIBUTION IS CONSTRUCTED IN THE SYSTEM IN WHICH THE TABULATED Legend

DATA ARE GIVEN (I.E., CM OR LAB - NO ATTEMPT IS MADE TO CONVERT Legend

FROM ONE SYSTEM TO THE OTHER). A MAXIMUM OF 60000 POINTS IS ALLOWE Legend

TO REPRESENT THE ANGULAR DISTRIBUTION AT EACH ENERGY. Legend

Legend

ELIMINATION OF NEGATIVE VALUES Legend

------------------------------ Legend

THE RECONSTRUCTED ANGULAR DISTRIBUTION WILL BE TESTED AND IF IT Legend

IS NEGATIVE AT ONE OR MORE COSINES AN ERROR MESSAGE WILL BE OUTPUT Legend

AND BASED ON THE INPUT OPTION SELECTED ONE OF THE FOLLOWING Legend

CORRECTIVE ACTIONS WILL BE TAKEN (SEE, INPUT OPTIONS), Legend

(1) NO CORRECTION Legend

(2) CHANGE ALL TABULATED VALUES TO FORCE DISTRIBUTION TO BE Legend

POSITIVE (MINIMUM MORE THAN 1 MILLI-BARN). THE MINIMUM VALUE Legend

MAY BE CHANGED BY INPUT. WITH THIS OPTION THERE IS NO Legend

RESTRICTION ON THE AMOUNT THAT EACH VALUE IS CHANGED AND AS Legend

SUCH THIS OPTION SHOULD BE USED WITH CAUTION AND ONLY AS A Legend

LAST RESORT IF NO OTHER APPROACH CAN BE USED TO MAKE THE Legend

DISTRIBUTION POSITIVE. Legend

Legend

OUTPUT Legend

------ Legend

THE OUTPUT WILL BE THE LINEARIZED ANGULAR DISTRIBUTION. THE Legend

TABULATED DISTRIBUTION WILL BE NORMALIZED TO UNITY BEFORE OUTPUT. Legend

Legend

CORRECTING NEGATIVE ANGULAR DISTRIBUTION Legend

---------------------------------------- Legend

IF AN ANGULAR DISTRIBUTION IS NEGATIVE AN ERROR MESSAGE WILL BE Legend

PRINTED AND THE USER MAY DECIDE (BASED ON INPUT OPTION) TO, Legend

(1) NOT PERFORM ANY CORRECTIVE ACTION. Legend

(2) FOR TABULATED DISTRIBUTIONS - ADD THE SAME VALUE TO EACH POINT Legend

VALUE SUCH THAT WHEN THE DISTRIBUTION IS RE-NORMALIZED THE Legend

MINIMUM VALUE IS 0.001 (1 MILLI-BARN). THE MINIMUM VALUE CAN Legend

BE CHANGED BY INPUT. WARNING...EXCEPT FOR SELECTION OF THE Legend

MINIMUM VALUE (BY INPUT) THE USER HAS NO CONTROL OVER HOW Legend

MUCH THE DISTRIBUTION IS CHANGED. THEREFORE THIS OPTION SHOULD Legend

BE USED WITH CAUTION. Legend

(3) FOR LEGENDRE COEFFICIENTS ONE OF TWO OPTIONS MAY BE SELECTED, Legend

(A) CHANGE INDIVIDUAL COEFFICIENTS (NO ONE COEFFICIENT BY MORE Legend

THAN 1 PER-CENT) TO MAKE THE DISTRIBUTION POSITIVE WITH A Legend

MINIMUM VALUE OF 0.001 (1 MILLI-BARN). THE MAXIMUM PER-CENT Legend

CHANGE IN EACH COEFFICIENT AND MINIMUM VALUE MAY BE CHANGED Legend

BY INPUT. INPUT THE PROGRAM CANNOT MAKE THE DISTRIBUTION Legend

POSITIVE BY CHANGING EACH COEFFICIENT BY UP TO THE MAXIMUM Legend

ALLOWABLE AMOUNT, THE ORIGINAL ANGULAR DISTRIBUTION OR Legend

COEFFICIENTS WILL BE OUTPUT. ONLY IN THE LATTER CASE SHOULD Legend

ONE CONSIDER USING OPTION (B) DESCRIBED BELOW. Legend

(B) LOGICALLY ADD THE SAME VALUE TO EACH POINT VALUE SUCH THAT Legend

WHEN THE DISTRIBUTION IS RE-NORMALIZED THE MINIMUM VALUE IS Legend

0.001 (1 MILLI-BARN). THIS IS EQUIVALENT AT INCREASING P0 Legend

BY A CERTAIN AMOUNT AND RE-NORMALIZATION IS EQUIVALENT TO THEN Legend

DIVIDING EACH COEFFICIENT BY A CERTAIN AMOUNT. THEREFORE, Legend

WHAT IS PHYSICALLY DONE BY THE PROGRAM IS TO DIVIDE EACH Legend

COEFFICIENT BY THE SAME AMOUNT. WARNING..EXCEPT FOR SELECTION Legend

OF THE MINIMUM VALUE (BY INPUT) THE USER HAS NO CONTROL OVER Legend

HOW MUCH THE DISTRIBUTION IS CHANGED. THEREFORE THIS OPTION Legend

SHOULD BE USED WITH CAUTION. Legend

Legend

WARNING MESSAGES FROM PROGRAM Legend

----------------------------- Legend

THE WARNING MESSAGES PRINTED BY THIS PROGRAM SHOULD ONLY BE Legend

CONSIDERED TO BE EXACTLY THAT..WARNINGS..NOT AN ABSOLUTE JUDGEMENT Legend

BY THIS PROGRAM THAT THERE IS SOMETHING WRONG WITH THE DATA. WHEN Legend

WARNING MESSAGES ARE PRINTED EXAMINE THE DATA AND EITHER TAKE NO Legend

ACTION (IF YOU FEEL THAT THE DATA IS O.K.) OR CORRECT THE DATA Legend

(IF YOU FEEL THAT THE DATA IS INCORRECT AND YOU CAN CORRECT IT). Legend

Legend

VALIDITY OF MODIFIED DATA Legend

------------------------- Legend

BEFORE BELIEVING AND USING DATA WHICH HAS BEEN MODIFIED (EITHER Legend

TABULATED ANGULAR DISTRIBUTIONS OR LEGENDRE COEFFICIENTS) THE USER Legend

SHOULD INSURE THAT THE MODIFIED DATA IS PHYSICALLY MORE ACCEPTABLE Legend

THAN THE ORIGINAL DATA. IN ORDER TO DO THIS ONE OR MORE OF THE Legend

FOLLOWING METHODS SHOULD BE USED, Legend

Legend

(1) USE THE ENERGY VARIATION TESTS BUILT-IN TO THIS PROGRAM AND Legend

EVALPLOT TO PLOT THE ENERGY DEPENDENCE OF THE LEGENDRE Legend

COEFFICIENTS IN ORDER TO IDENTIFY AND CORRECT (BY HAND...NOT Legend

BY THIS PROGRAM) ANY COEFFICIENTS WHICH HAVE UNREALISTIC Legend

ENERGY AND L ORDER VARIATIONS. THIS SHOULD ALWAYS BE DONE Legend

FIRST TO ELIMINATE MAJOR PROBLEMS BEFORE USING THIS PROGRAM Legend

TO AUTOMATICALLY MAKE MINOR CORRECTIONS. Legend

(1) OUTPUT AND PLOT THE UNCORRECTED AND CORRECTED ANGULAR Legend

DISTRIBUTIONS. COMPARE THE PLOTS TO INSURE THAT THE CORRECTED Legend

DATA DOES NOT SERIOUSLY CHANGE THE ENERGY DEPENDENCE OF THE Legend

ANGULAR DISTRIBUTION. Legend

(2) IF PLOTTING CAPABILITY IS NOT AVAIALABLE, USE THE PRINTED OUT Legend

OF THIS PROGRAM TO DETERMINE HOW MUCH THE TABULATED ANGULAR Legend

DISTRIBUTION OR LEGENDRE COEFFICIENTS HAVE BEEN MODIFIED. Legend

GENERALLY IF ONE COEFFICIENT HAS BEEN ONLY SLIGHTLY MODIFIED Legend

THE DISTRIBUTION WILL BE ACCEPTABLE. HOWEVER IF MANY Legend

COEFFICIENTS HAVE BEEN MODIFIED THE RESULT WILL NOT BE Legend

RELIABLE. Legend

Legend

SEEING ANGULAR DISTRIBUTIONS AND LEGENDRE COEFFICIENTS Legend

------------------------------------------------------ Legend

PROGRAM EVALPLOT CAN BE USED TO PLOT ANGULAR DISTRIBUTION AND Legend

LEGENDRE COEFFICIENTS - WHEN IT COMES TO CHECKING THIS TYPE OF Legend

DATA THERE IS NO SUBSTITUTE FOR PLOTS OF THE DATA TO MAKE THE Legend

JOB EASY AND STRAIGHTFORWARD. Legend

Legend

FOR LEGENDRE COEFFICIENTS EVALPLOT CAN BE USED TO SEE THE ENERGY Legend

DEPENDENCE OF EACH COEFFICIENT - THIS IS AN EXTREMELY EASY AND Legend

USEFUL WAY TO CHECK FOR ERRORS IN THE BASIC DATA. Legend

Legend

FOR ANGULAR DISTRIBUTION EVALPLOT CAN BE USED TO PLOT THEM AT Legend

EACH ENERGY THAT THEY ARE TABULATED - THIS IS ALSO AN EASY AND Legend

USEFUL WAY TO CHECK FOR ERRORS. Legend

Legend

I/O UNIT DEFINITIONS Legend

-------------------- Legend

UNIT DESCRIPTION Legend

---- ----------- Legend

2 INPUT CARDS Legend

3 OUTPUT REPORT Legend

10 ORIGINAL DATA IN ENDF/B FORMAT Legend

11 FINAL DATA IN ENDF/B FORMAT Legend

Legend

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Legend

--------------------------------------------------------------- Legend

UNIT FILE NAME Legend

---- ---------- Legend

2 LEGEND.INP Legend

3 LEGEND.LST Legend

10 ENDFB.IN Legend

11 ENDFB.OUT Legend

Legend

INPUT CARD Legend

---------- Legend

CARD COLS. FORMAT DESCRIPTION Legend

---- ----- ------ ----------- Legend

1 1-11 E11.4 FRACTIONAL THINNING CRITERIA Legend

12-22 I11 MAXIMUM NUMBER OF POINTS IN ANGULAR DISTRIBUTION Legend

RECONSTRUCTED FROM LEGENDRE COEFFICIENTS (PRESENT Legend

LIMITS ARE 11 TO 60000 POINTS) Legend

*THIS OPTION CAN BE USED TO RUN QUICK, BUT NOT Legend

NECESSARILY SO ACCURATE CALCULATIONS - TO ROUGHLY Legend

SEE WHAT THE ANGULAR DISTRIBUTIONS LOOK LIKE. Legend

*IT IS RECOMMENDED THAT YOU USE 0 AS INPUT - IN Legend

WHICH CASE THE PROGRAM WILL USE THE MAXIMUM Legend

ALLOWABLE NUMBER OF POINTS = 60000. Legend

23-33 I11 TABULATED ANGULAR DISTRIBUTION TREATMENT Legend

= 0 - COPY TABLES Legend

= 1 - LINEARIZE TABLES (OUTPUT TABLES) Legend

= 2 - LINEARIZE AND THIN TABLES (OUTPUT TABLES) Legend

34-44 I11 LEGENDRE COEFFICIENT TREATMENT Legend

= 0 - COPY LEGENDRE COEFFICIENTS Legend

= 1 - RECONSTRUCT TABULATED ANGULAR DISTRIBUTION. Legend

(OUTPUT TABLES). Legend

= 2 - RECONSTRUCT TABULATED ANGULAR DISTRIBUTION. Legend

(OUTPUT LEGENDRE COEFFICIENTS). Legend

45-55 I11 NEGATIVE ANGULAR DISTRIBUTION TREATMENT. Legend

= 0 - NO CORRECTION Legend

= 1 - TABULATE DATA - NO CORRECTION. Legend

- LEGENDRE DATA - CHANGE COEFFICIENTS Legend

(NONE BY MORE THAN 1.0 PER-CENT - CAN BE Legend

CHANGED BY INPUT). Legend

= 2 - FORCE DISTRIBUTIONS TO BE POSITIVE Legend

(TABULATED OR LEGENDRE DATA). Legend

56-66 I11 LEGENDRE COEFFICIENT VARIATION TEST FLAG. Legend

= 0 - TEST TESTS. Legend

= 1 - PERFORM TESTS, Legend

(A) LEGENDRE ORDER INCREASES WITH ENERGY. Legend

(C) MONOTONIC VARIATION OF COEFFICIENTS Legend

AS A FUNCTION OF ENERGY. Legend

(C) COEFFICIENTS DECREASE AS A FUNCTION OF Legend

LEGENDRE ORDER. Legend

2 1-60 60A1 ENDF/B INPUT DATA FILENAME Legend

(STANDARD OPTION = ENDFB.IN) Legend

3 1-60 60A1 ENDF/B OUTPUT DATA FILENAME Legend

(STANDARD OPTION = ENDFB.OUT) Legend

4-N 1- 6 I6 LOWER MAT LIMIT Legend

7- 8 I2 LOWER MF LIMIT Legend

9-11 I3 LOWER MT LIMIT Legend

12-17 I6 UPPER MAT LIMIT Legend

18-19 I2 UPPER MF LIMIT Legend

20-22 I3 UPPER MT LIMIT Legend

23-33 E11.4 LOWER ENERGY LIMIT Legend

34-44 E11.4 UPPER ENERGY LIMIT Legend

45-55 E11.4 MINIMUM ALLOWABLE VALUE OF ANGULAR DISTRIBUTION Legend

56-66 E11.4 ALLOWABLE FRACTION (NOT PER-CENT) CHANGE IN ANY Legend

ONE LEGENDRE COEFFICIENT TO MAKE THE ANGULAR Legend

DISTRIBUTION POSITIVE (AND AT LEAST EQUAL TO THE Legend

INPUT MINIMUM ALLOWABLE VALUE). Legend

Legend

*UP TO 100 MAT/MT/E RANGES MAY BE INPUT, EACH SPECIFYING AN Legend

ALLOWABLE MINIMUM SIGMA AND MAXIMUM CHANGE IN COEFFICIENTS. Legend

*INPUT IS TERMINATED BY A BLANK CARD. Legend

*ALL MAY/MT/E RANGES NOT SPECIFIED BY INPUT WILL BE TREATED BY Legend

ALLOWING A MINIMUM SIGMA OF 0.001 (1 MILLI-BARN) AND A CHANGE Legend

IN EACH COEFFICIENT BY UP TO 0.01 (1 PER-CENT). Legend

*THESE MAT/MT/E RANGES ARE NOT USED TO CORRECT ALL ANGULAR Legend

DISTRIBUTIONS WHERE SIGMA IS LESS THAN THE MINIMUM. THEY ARE Legend

ONLY USED TO CORRECT DISTRIBUTION THAT ARE NEGATIVE AND TO Legend

INSURE THAT THE CROSS SECTION AT THE COSINES WHERE THE ANGULAR Legend

DISTRIBUTION ARE INITIALLY NEGATIVE ARE CORRECTED TO BE POSITIVE Legend

AND AT LEAST AS LARGE AS THE MINIMUM ALLOWABLE SIGMA (SPECIFIED Legend

BY INPUT). Legend

Legend

EXAMPLE INPUT NO. 1 Legend

------------------- Legend

PROCESS BOTH LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN Legend

ANGULAR DISTRIBUTION WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT Legend

AND OUTPUT UNCORRECTED TABULATED ANGULAR DISTRIBUTION USING Legend

A MAXIMUM OF 501 POINTS IN EACH TABULATED ANGULAR DISTRIBUTION. Legend

SINCE LEGENDRE COEFFICIENTS WILL NOT BE CORRECTED THE INPUT NEED Legend

NOT SPECIFY MAT/MT/E RANGES. Legend

Legend

READ /ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT Legend

Legend

THE FOLLOWING 4 INPUT LINES ARE REQUIRED, Legend

Legend

1.00000- 3 501 2 1 0 Legend

/ENDFB6/K300/LEAD.IN Legend

/ENDFB6/K300/LEAD.OUT Legend

(BLANK CARD TERMINATED INPUT) Legend

Legend

EXAMPLE INPUT NO. 2 Legend

------------------- Legend

PROCESS BOTH LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN Legend

ANGULAR DISTRIBUTION WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT Legend

AND OUTPUT CORRECTED TABULATED ANGULAR DISTRIBUTION (ONLY THOSE Legend

RE-CONSTRUCTED FROM LEGENDRE COEFFICIENTS WILL BE CORRECTED). Legend

FOR ALL MAT/MT/E CORRECT NEGATIVE ANGULAR DISTRIBUTION TO A VALUE Legend

OF 0.01 (10 MILLI-BARNS) AND ALLOW LEGENDRE COEFFICIENTS TO BE Legend

CHANGED BY UP TO 0.02 (2 PER-CENT). Legend

Legend

USE THE DEFAULT FILENAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE Legend

DONE BY LEAVING THE SECOND AND THIRD INPUT LINES BLANK). Legend

Legend

THE FOLLOWING 5 INPUT LINES ARE REQUIRED, Legend

Legend

1.00000- 3 501 2 1 1 Legend

Legend

Legend

1 1 1 999999999 0.00000+ 0 3.00000+ 7 1.00000- 2 2.00000- 2 Legend

(BLANK CARD TERMINATED INPUT) Legend

Legend

EXAMPLE INPUT NO. 3 Legend

------------------- Legend

PROCESS BOTH LEGENDRE COEFFICIENTS AND TABULATED DATA TO OBTAIN Legend

ANGULAR DISTRIBUTION WHICH ARE ACCURATE TO WITHIN 0.1 PER-CENT Legend

AND OUTPUT CORRECTED LEGENDRE COEFFICIENTS AND UNCORRECTED Legend

TABULATED ANGULAR DISTRIBUTIONS. FOR MAT=1800, MT=2 CORRECT Legend

NEGATIVE ANGULAR DISTRIBUTIONS TO INSURE THE MINIMUM IS 0.01 Legend

(10 MILLI-BARNS) ALLOWING EACH LEGENDRE COEFFICIENT TO CHANGE BY Legend

UP TO 0.02 (2 PER-CENT). ALL OTHER MAT/MT/E WILL BE CORRECTED Legend

TO A MINIMUM OF 0.001 (1 MILLI-BARN) ALLOWING A 0.01 (1 PER-CENT) Legend

CHANGE (BUILT-IN OPTION). Legend

Legend

READ /ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT Legend

Legend

THE FOLLOWING 5 INPUT LINES ARE REQUIRED, Legend

Legend

1.00000- 3 501 2 2 1 Legend

/ENDFB6/K300/LEAD.IN Legend

/ENDFB6/K300/LEAD.OUT Legend

1800 4 2 1800 4 2 0.00000+ 0 3.00000+ 7 1.00000- 2 2.00000- 2 Legend

(BLANK CARD TERMINATED INPUT) Legend

Legend

EXAMPLE INPUT NO. 4 Legend

------------------- Legend

TO COPY TABULATED ANGULAR DISTRIBUTION AND CONVERT LEGENDRE Legend

COEFFICIENTS TO UNCORRECTED TABULAR DISTRIBUTIONS. Legend

Legend

USE THE DEFAULT FILENAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE Legend

DONE BY LEAVING THE SECOND AND THIRD INPUT LINES BLANK). Legend

Legend

THE FOLLOWING 4 INPUT LINES ARE REQUIRED, Legend

Legend

1.00000- 3 501 0 1 0 Legend

Legend

Legend

(BLANK CARD TERMINATED INPUT) Legend

Legend

======================================================================= Legend

======================================================================= Linear

Linear

PROGRAM LINEAR Linear

VERSION 74-1 (MAY 1974) Linear

VERSION 75-1 (APRIL 1975) Linear

VERSION 76-2 (OCTOBER 1976) Linear

VERSION 77-1 (JANUARY 1977) Linear

VERSION 78-1 (JULY 1978) Linear

VERSION 79-1 (JULY 1979) CDC-7600 AND CRAY-1 VERSION. Linear

VERSION 80-1 (MAY 1980) IBM, CDC AND CRAY VERSION. Linear

VERSION 80-2 (DECEMBER 1980) Linear

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ENERGY POINTS FROM EVALUATION. Linear

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VERSION 83-2 (OCTOBER 1983) IMPROVED BASED ON USER COMMENTS. Linear

VERSION 84-1 (APRIL 1984) IMPROVED BASED ON USER COMMENTS. Linear

VERSION 84-2 (JUNE 1984) *UPDATED FOR ENDF/B-VI FORMATS. Linear

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VERSION 85-1 (AUGUST 1985) *FORTRAN-77/H VERSION Linear

VERSION 86-1 (JANUARY 1986)*ENDF/B-VI FORMAT Linear

VERSION 87-1 (JANUARY 1987)*DOUBLE PRECISION TREATMENT OF CROSS Linear

SECTION Linear

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Linear

FILE NAMES (SEE, SUBROUTINE FILEIO Linear

FOR DETAILS). Linear

*IMPROVED BASED ON USER COMMENTS. Linear

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Linear

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KEYWORDS. Linear

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HAS BEEN CHANGED...SEE DESCRIPTION Linear

BELOW. Linear

VERSION 91-1 (JULY 1991) *ADDED INTERPOLATION LAW 6 - ONLY USED Linear

FOR CHARGED PARTICLE CROSS SECTIONS Linear

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THE SPONTANEOUS NU-BAR IS NOT AN Linear

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*CLOSE ALL FILES BEFORE TERMINATING Linear

(SEE, SUBROUTINE ENDIT) Linear

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60000 POINTS Linear

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USER FEEDBACK Linear

VERSION 99-2 (JUNE 1999) *ASSUME ENDF/B-VI, NOT V, IF MISSING Linear

MF=1, MT-451. Linear

VERS. 2000-1 (FEBRUARY 2000)*ADDED MF = 9 AND 10 LINEARIZATION Linear

*GENERAL IMPROVEMENTS BASED ON Linear

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Linear

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AUTHORS MESSAGE Linear

--------------- Linear

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Linear

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Linear

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Linear

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION. Linear

Linear

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Linear

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Linear

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Linear

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Linear

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Linear

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Linear

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Linear

COMPUTER. Linear

Linear

PURPOSE Linear

------- Linear

THIS PROGRAM IS DESIGNED TO CONVERT ENDF/B FILE 3, 23 AND 27 DATA Linear

TO LINEAR-LINEAR INTERPOLABLE FORM. ANY SECTION THAT IS ALREADY Linear

LINEAR-LINEAR INTERPOLABLE WILL BE THINNED. Linear

Linear

IN THE FOLLOWING DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY Linear

---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE Linear

TAPE, CARDS, DISK OR ANY OTHER MEDIUM. Linear

Linear

ENDF/B FORMAT Linear

------------- Linear

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Linear

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Linear

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Linear

Linear

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Linear

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Linear

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Linear

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Linear

CORRECTLY OUTPUT ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451 Linear

AND ALL SECTIONS OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL Linear

OTHER SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO Linear

THE CORRECTNESS OR INCORRECTNESS OF ALL OTHER SECTIONS. Linear

Linear

OUTPUT FORMAT Linear

------------- Linear

IN THIS VERSION OF LINEAR ALL ENERGIES WILL BE OUTPUT IN Linear

F (INSTEAD OF E) FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN Linear

WITH UP TO 9 DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN Linear

OUTPUT OPTION. HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS Linear

OF ENERGIES WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6 DIGITS Linear

TO THE 9 DIGIT OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE Linear

TO USE THE 9 DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA Linear

DUE TO TRUNCATION OF ENERGIES TO 6 DIGITS DURING OUTPUT. Linear

Linear

CONTENTS OF OUTPUT Linear

------------------ Linear

ENTIRE EVALUATIONS ARE OUTPUT, NOT JUST THE LINEARIZED DATA Linear

CROSS SECTIONS, E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO Linear

INCLUDED. Linear

Linear

DOCUMENTATION Linear

------------- Linear

THE FACT THAT THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED Linear

BY THE ADDITION OF 3 COMMENT LINES AT THE END OF EACH HOLLERITH Linear

SECTION IN THE FORM Linear

Linear

***************** PROGRAM LINEAR (2004-1) **************** Linear

FOR ALL DATA GREATER THAN 1.00000-10 IN ABSOLUTE VALUE Linear

DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.1 PER-CENT Linear

Linear

THE ORDER OF SIMILAR COMMENTS (FROM RECENT, SIGMA1 AND GROUPIE) Linear

REPRESENTS A COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON Linear

THE DATA BY THESE PROGRAMS. Linear

Linear

THESE COMMENT LINES ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Linear

I.E., THIS PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Linear

OF THE HOLLERITH SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF Linear

EARLIER VERSIONS OF ENDF/B. BY READING AN EXISTING MF=1, MT=451 Linear

IT IS POSSIBLE FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF Linear

THE ENDF/B FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF Linear

MF=1, MT=451 PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO Linear

DETERMINE WHICH VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND Linear

AS SUCH IT IS IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT Linear

SHOULD BE USED TO CREATE A HOLLERITH SECTION. Linear

Linear

REACTION INDEX Linear

-------------- Linear

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Linear

SECTION MF=1, MT=451 OF EACH EVALUATION. Linear

Linear

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Linear

THIS CONVENTION HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT Linear

REQUIRE A CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Linear

NOT CONSIDERED WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING Linear

A CORRECT REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE Linear

A REACTION INDEX FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Linear

YOU MAY USE PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX. Linear

Linear

SECTION SIZE Linear

------------ Linear

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Linear

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Linear

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Linear

Linear

FOR ANY LINEARIZED SECTION THAT CONTAINS 60000 OR FEWER POINTS Linear

THE ENTIRE OPERATION WILL BE PERFORMED IN CORE AND THE LINEARIZED Linear

DATA WILL BE OUTPUT DIRECTLY TO THE ENDF/B FORMAT. FOR ANY SECTION Linear

THAT CONTAINS MORE POINTS THE DATA WILL BE LINEARIZED A PAGE AT A Linear

TIME (1 PAGE = 60000 POINTS) AND OUTPUT TO SCRATCH. AFTER THE Linear

ENTIRE SECTION HAS BEEN LINEARIZED THE DATA WILL BE READ BACK FROM Linear

SCRATCH AND OUTPUT TO THE ENDF/B FORMAT. Linear

Linear

SELECTION OF DATA Linear

----------------- Linear

THE PROGRAM SELECTS DATA TO BE LINEARIZED BASED EITHER ON EITHER Linear

MAT (ENDF/B MAT NO.) OR ZA AS WELL AS MF AND MT NUMBERS. THIS Linear

PROGRAM ALLOWS UP TO 100 MAT/MF/MT OR ZA/MF/MT RANGES TO BE Linear

SPECIFIED BY INPUT PARAMETERS. THE PROGRAM WILL ASSUME THAT THE Linear

ENDF/B TAPE IS IN MAT ORDER, REGARDLESS OF THE CRITERIA USED Linear

TO RETRIEVE MATERIALS. IF RETRIEVAL IS BY MAT RANGE THE PROGRAM Linear

WILL TERMINATE WHEN A MAT IS FOUND THAT IS ABOVE ALL REQUESTED Linear

MAT RANGES. IF RETRIEVAL IS BY ZA RANGE THE PROGRAM WILL SEARCH Linear

THE ENTIRE ENDF/B TAPE. Linear

Linear

PROGRAM OPERATION Linear

----------------- Linear

EACH SECTION OF DATA IS CONSIDERED SEPARATELY. EACH SECTION OF Linear

ENDF/B DATA TO LINEARIZE IS REPRESENTED BY A TABLE OF ENERGY Linear

VS. CROSS SECTION AND ANY ONE OF FIVE ALLOWABLE INTERPOLATION LAWS Linear

BETWEEN ANY TWO TABULATED POINTS. THIS PROGRAM WILL REPLACE EACH Linear

SECTION OF DATA CROSS SECTIONS BY A NEW TABLE OF ENERGY VS. Linear

CROSS SECTION IN WHICH THE INTERPOLATION LAW IS ALWAYS LINEAR IN Linear

ENERGY AND CROSS SECTION BETWEEN ANY TWO TABULATED POINTS. Linear

Linear

DATA IS READ AND LINEARIZED A PAGE AT A TIME (ONE PAGE CONTAINS Linear

60000 DATA POINTS). IF THE FINAL LINEARIZED SECTION CONTAINS TWO Linear

PAGES OR LESS, DATA POINTS IT WILL BE ENTIRELY CORE RESIDENT Linear

AFTER IT HAS BEEN LINEARIZED AND WILL BE WRITTEN DIRECTLY FROM Linear

CORE TO THE OUTPUT TAPE. IF THE LINEARIZED SECTION IS LARGER THAN Linear

TWO PAGES, AFTER EACH PAGE IS LINEARIZED IT WILL BE WRITTEN TO Linear

SCRATCH. AFTER THE ENTIRE SECTION HAS BEEN LINEARIZED IT WILL Linear

BE READ BACK FROM SCRATCH, TWO PAGES AT A TIME, AND WRITTEN TO Linear

THE OUTPUT TAPE. Linear

Linear

KEEP EVALUATED DATA POINTS Linear

-------------------------- Linear

SOMETIMES IT IS CONVENIENT TO KEEP ALL ENERGY POINTS WHICH WERE Linear

PRESENT IN THE ORIGINAL EVALUATION AND TO MERELY SUPPLEMENT THESE Linear

POINTS WITH ADDITIONAL ENERGY POINTS IN ORDER TO LINEARIZE THE Linear

CROSS SECTIONS. FOR EXAMPLE, IT IS OFTEN CONVENIENT TO KEEP THE Linear

THERMAL VALUE (AT 0.0253 EV) OR THE VALUE AT 14.1 MEV. Linear

Linear

THE CURRENT VERSION OF THIS PROGRAM WILL ALLOW THE USER TO KEEP Linear

ALL ORIGINAL EVALUATED DATA POINTS BY SPECIFYING 1 IN COLUMNS Linear

34-44 OF THE FIRST INPUT LINE. THIS WILL TURN OFF THE BACKWARD Linear

THINNING (SEE UCRL-50400, VOL. 17, PART A FOR EXPLANATION) AND Linear

RESULT IN ALL ORIGINAL ENERGY POINTS BEING KEPT. CAUTION SHOULD Linear

BE EXERCISED IN USING THIS OPTION SINCE IT CAN RESULT IN A Linear

CONSIDERABLE INCREASE IN THE NUMBER OF DATA POINTS OUTPUT BY Linear

THIS CODE. Linear

Linear

FOR ALL USERS WHO ARE NOT INTERESTED IN THIS OPTIONS NO CHANGES Linear

ARE REQUIRED IN THE INPUT TO THIS PROGRAM, I. E. IF COLUMNS Linear

34-44 ARE BLANK (AS FOR ALL PREVIOUS VERSIONS OF THIS CODE) THE Linear

PROGRAM WILL OPERATE EXACTLY AS IT DID BEFORE. Linear

Linear

ALLOWABLE ERROR Linear

--------------- Linear

ALLOWABLE ERROR MUST ALWAYS BE SPECIFIED IN THE INPUT TO THIS Linear

PROGRAM AS A FRACTION, NOT A PER-CENT. FOR EXAMPLE, INPUT THE Linear

ALLOWABLE FRACTIONAL ERROR 0.001 IN ORDER TO OBTAIN DATA THAT IS Linear

ACCURATE TO WITHIN 0.1 PER-CENT. Linear

Linear

THE CONVERSION OF THE DATA FROM THE GENERAL INTERPOLATION FORM TO Linear

LINARLY INTERPOLABLE FORM CANNOT BE PERFORMED EXACTLY. HOWEVER, IT Linear

CAN BE PERFORMED TO VIRTUALLY ANY REQUIRED ACCURACY AND MOST Linear

IMPORTANTLY CAN BE PERFORMED TO A TOLERANCE THAT IS SMALL COMPARED Linear

TO THE UNCERTAINTY IN THE CROSS SECTIONS THEMSELVES. AS SUCH THE Linear

CONVERSION OF CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM CAN BE Linear

PERFORMED WITH ESSENTIALLY NO LOSE OF INFORMATION. Linear

Linear

THE ALLOWABLE ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Linear

DEPENDENT. THE ALLOWABLE ERROR IS DESCRIBED BY A TABULATED Linear

FUNCTION OF UP TO 20 (ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Linear

BETWEEN TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Linear

ERROR WILL BE CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE. Linear

WITH THIS ENERGY DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR Linear

ANY GIVEN APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE Linear

OF INTEREST AND A LESS STRINGENT ERROR IN OTHER ENERGY RANGES. Linear

Linear

DEFAULT ALLOWABLE ERROR Linear

----------------------- Linear

IN ORDER TO INSURE CONVERGENCE OF THE LINEARIZING ALGORITHM THE Linear

ALLOWABLE ERROR MUST BE POSITIVE. IF THE USER INPUTS AN ERROR Linear

THAT IS NOT POSITIVE IT WILL AUTOMATICALLY BE SET TO THE DEFAULT Linear

VALUE (CURRENTLY 0.001, CORRESPONDING TO 0.1 PER-CENT) AND Linear

INDICATED AS SUCH IN THE OUTPUT LISTING. Linear

Linear

COULOMB PENETRABILITY (INTERPOLATION LAW = 6) Linear

-------------------------------------------- Linear

INTRODUCED FOR ENDF/B-VI. THIS IS DEFINED AS, Linear

Linear

SIG(E) = C1*EXP(-C2/SQRT(E - T)) Linear

Linear

THIS PROGRAM ONLY CONSIDERS EXOTHERMIC REACTIONS - T = 0 Linear

Linear

SIG(E) = C1*EXP(-C2/SQRT(E)) Linear

Linear

WARNING...THIS INTERPOLATION LAW SHOULD ONLY BE USED FOR REACTIONS Linear

WHICH HAVE A POSITIVE Q-VALUE (EXOTHERMIC REACTIONS), Linear

SINCE HERE WE ONLY CONSIDER T = 0.0 IN THE FORMALISM. Linear

IN ALL OTHER CASES A WARNING MESSAGE WILL BE PRINTED. Linear

Linear

INPUT FILES Linear

----------- Linear

UNIT DESCRIPTION Linear

---- ----------- Linear

2 INPUT LINES (BCD - 80 CHARACTERS/RECORD) Linear

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Linear

Linear

OUTPUT FILES Linear

------------ Linear

UNIT DESCRIPTION Linear

---- ----------- Linear

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Linear

11 FINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Linear

Linear

SCRATCH FILES Linear

------------- Linear

UNIT DESCRIPTION Linear

---- ----------- Linear

12 SCRATCH FILE (BINARY - 180000 WORDS/RECORD Linear

Linear

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILEIO) Linear

---------------------------------------------------- Linear

UNIT FILE NAME Linear

---- ---------- Linear

2 LINEAR.INP Linear

3 LINEAR.LST Linear

10 ENDFB.IN Linear

11 ENDFB.OUT Linear

12 (SCRATCH) Linear

Linear

Linear

INPUT PARAMETERS Linear

---------------- Linear

FOR VERSIONS EARLIER THAN 90-1 THIS PROGRAM ONLY ALLOWED THE USER Linear

TO SPECIFY BY INPUT PARAMETERS WHICH MATERIALS (MAT) TO PROCESS. Linear

FOR EACH REQUESTED MATERIAL NEUTRON INTERACTION CROSS SECTIONS Linear

(MF=3) WOULD BE LINEARIZED AND THE REMAINDER OF THE MATERIAL Linear

WOULD BE COPIED. Linear

Linear

FOR VERSIONS 90-1 AND LATER THIS PROGRAM WILL ALLOW THE USER TO Linear

TO SPECIFY BY INPUT PARAMETERS EXACTLY WHAT SECTIONS OF DATA Linear

TO PROCESS. FOR EACH SECTION OF DATA, SPECIFIED BY MAT, MF, MT Linear

RANGES, SECTIONS OF MF=3, 23 AND 27 WILL BE LINEARIZED AND ALL Linear

OTHER REQUESTED SECTIONS WILL BE COPIED. ALL SECTIONS WHICH ARE Linear

NOT EXPLICITLY REQUESTED WILL BE SKIPPED AND WILL NOT APPEAR ON Linear

ENDF/B FILE OUTPUT BY THIS PROGRAM. Linear

Linear

WITH THIS NEW PROCEDURE YOU CAN MINIMIZE THE SIZE OF THE ENDF/B Linear

FILE OUTPUT BY THIS PROGRAM, E.G., IF YOU ONLY WANT NEUTRON Linear

CROSS SECTIONS FOR SUBSEQUENT PROCESSING YOU NEED ONLY REQUEST Linear

ONLY MF=3 DATA. Linear

Linear

HOWEVER, YOU MUST UNDERSTAND THAT ONLY THOSE SECTIONS WHICH YOU Linear

EXPLICITLY REQUEST WILL APPEAR ON THE ENDF/B FILE OUTPUT BY Linear

THIS PROGRAM. FOR EXAMPLE, IF YOU WISH TO DOCUMENT EXACTLY Linear

HOW YOU LINEARIZED THE DATA BY INCLUDING COMMENTS IN MF=1, MT=451 Linear

THEN YOU MUST EXPLICITLY REQUEST THAT MF=1, MT=451 BE PROCESSED Linear

FOR EACH MATERIAL THAT YOU REQUEST. SIMILAR IF YOU WANT THE Linear

ENTIRE EVALUATION YOU MUST REQUEST ALL MF AND MT TO BE OUTPUT. Linear

Linear

LINE COLS. DESCRIPTION Linear

---- ----- ----------- Linear

1 1-11 SELECTION CRITERIA (0=MAT, 1=ZA) Linear

12-22 MONITOR MODE SELECTOR Linear

= 0 - NORMAL OPERATION Linear

= 1 - MONITOR PROGRESS OF LINEARIZING OF THE DATA. Linear

EACH TIME A PAGE OF DATA POINTS IS WRITTEN TO Linear

THE SCRATCH FILE PRINT OUT THE TOTAL NUMBER OF Linear

POINTS ON SCRATCH AND THE LOWER AND UPPER Linear

ENERGY LIMITS OF THE PAGE (THIS OPTION MAY BE Linear

USED IN ORDER TO MONITOR THE EXECUTION SPEED Linear

OF LONG RUNNING JOBS). Linear

23-33 MINIMUM CROSS SECTION OF INTEREST (BARNS). Linear

(IF 0.0 OR LESS IS INPUT THE PROGRAM WILL Linear

USE 1.0E-10). ENERGY INTERVALS WILL NOT BE Linear

SUB-DIVIDED IF THE ABSOLUTE VALUE OF THE CROSS Linear

SECTION WITHIN THE INTERVAL IS LESS THAN THIS VALUE. Linear

AN EXCEPTION TO THIS RULE IS NEAR THRESHOLDS ENERGY Linear

INTERVALS WILL BE SUB-DIVIDED UNTIL CONVERGENCE Linear

REGARDLESS OF THE MAGNITUDE OF THE CROSS SECTION. Linear

34-44 KEEP ORIGINAL EVALUATED DATA POINTS. Linear

= 0 - NO. Linear

= 1 - YES - ADDITIONAL POINTS MAY BE ADDED IN ORDER Linear

TO LINEARIZE DATA, BUT ALL ORIGINAL Linear

DATA POINTS WILL BE INCLUDED IN THE Linear

RESULTS. Linear

2 1-60 ENDF/B INPUT DATA FILENAME Linear

(STANDARD OPTION = ENDFB.IN) Linear

3 1-60 ENDF/B OUTPUT DATA FILENAME Linear

(STANDARD OPTION = ENDFB.OUT) Linear

4-N 1- 6 LOWER MAT OR ZA LIMIT Linear

7- 8 LOWER MF LIMIT Linear

9-11 LOWER MT LIMIT Linear

12-17 UPPER MAT OR ZA LIMIT Linear

18-19 UPPER MF LIMIT Linear

20-22 UPPER MT LIMIT Linear

UP TO 100 RANGES MAY BE SPECIFIED, ONLY ONE RANGE Linear

PER LINE. THE LIST OF RANGES IS TERMINATED BY A Linear

BLANK LINE. IF THE UPPER MAT LIMIT OF ANY REQUEST Linear

IS LESS THAN THE LOW LIMIT IT WILL BE SET EQUAL TO Linear

THE LOWER LIMIT. IF THE UPPER LIMIT IS STILL ZERO Linear

IT WILL BE SET EQUAL TO 999999. IF THE UPPER MF OR Linear

MT LIMIT IS ZERO IT WILL BE SET TO 99 OR 999 Linear

RESPECTIVELY. Linear

VARY 1-11 ENERGY FOR ERROR LAW Linear

12-22 ALLOWABLE FRACTIONAL ERROR FOR ERROR LAW. Linear

THE ACCEPTABLE LINEARIZING ERROR MAY BE SPECIFIED TO Linear

BE EITHER ENERGY INDEPENDENT (DEFINED BY A SINGLE Linear

ERROR), OR ENERGY DEPENDENT (DEFINED BY UP TO 20 Linear

ENERGY, ERROR PAIRS). FOR THE ENERGY DEPENDENT CASE Linear

LINEAR INTERPOLATION WILL BE USED TO DEFINE THE ERROR Linear

AT ENERGIES BETWEEN THOSE AT WHICH IT IS TABULATED. Linear

IN ALL CASES THE ERROR LAW IS TERMINATED BY A BLANK Linear

LINE. IF ONLY ONE ENERGY, ERROR PAIR IS GIVEN THE Linear

THE LAW WILL BE CONSIDERED TO BE ENERGY INDEPENDENT. Linear

IF MORE THAN ONE PAIR IS GIVEN IT WILL BE CONSIDERED Linear

TO BE ENERGY DEPENDENT (NOTE, ENERGY INDEPENDENT Linear

FORM WILL RUN FASTER THAN THE EQUIVALENT ENERGY Linear

DEPENDENT FORM). FOR AN ENERGY DEPENDENT ERROR LAW Linear

ALL ENERGIES MUST BE ASCENDING ENERGY ORDER. FOR Linear

CONVERGENCE OF THE LINEARIZING ALGORITHM ALL ERRORS Linear

MUST BE POSITIVE. IF AN ALLOWABLE ERROR IS NOT Linear

POSITIVE IT WILL BE SET EQUAL TO THE STANDARD OPTION Linear

(CURRENTLY 0.001, CORRESPONDING TO 0.1 PER-CENT). Linear

IF THE FIRST ERROR LINE IS BLANK IT WILL TERMINATE Linear

THE ERROR LAW AND THE ERROR WILL BE TREATED AS Linear

ENERGY INDEPENDENT, EQUAL TO THE STANDARD OPTION Linear

(CURRENTLY 0.1 PER-CENT). (SEE EXAMPLE INPUT 4). Linear

Linear

EXAMPLE INPUT NO. 1 Linear

------------------- Linear

RETRIEVE DATA BY ZA IN ORDER TO FIND ALL URANIUM ISOTOPES AND Linear

THORIUM 232. RETRIEVE ALL NEUTRON INTERACTION CROSS SECTIONS Linear

(MF=3). ALL ENERGY INTERVALS IN WHICH THE CROSS SECTION IS Linear

AT LEAST 1 MICRO-BARN (1.0E-06 BARNS) WILL BE SUBDIVIDED. Linear

BACKWARD THINNING WILL BE PERFORMED. FROM 0 TO 100 EV LINEARIZE Linear

TO WITHIN 0.1 PER-CENT ACCURACY. FROM 100 EV TO 1 KEV VARY Linear

ACCURACY BETWEEN 0.1 AND 1.0 PER-CENT. ABOVE 1 KEV USE 1 Linear

PER-CENT ACCURACY. Linear

Linear

EXPLICITLY SPECIFY THE STANDARD FILENAMES. Linear

Linear

IN THIS CASE THE FOLLOWING 11 INPUT LINES ARE REQUIRED Linear

Linear

1 0 1.00000- 6 0 Linear

ENDFB.IN Linear

ENDFB.OUT Linear

92000 3 0 92999 3999 Linear

90232 3 0 0 3 0 (UPPER LIMIT AUTOMATICALLY SET TO 90232 3999) Linear

(END OF REQUEST LIST) Linear

0.00000+ 0 1.00000-03 Linear

1.00000+ 2 1.00000-03 Linear

1.00000+ 3 1.00000-02 Linear

1.00000+ 9 1.00000-02 Linear

(END OF ERROR LAW) Linear

Linear

EXAMPLE INPUT NO. 2 Linear

------------------- Linear

SAME AS THE ABOVE CASE, EXCEPT LINEARIZE ALL DATA TO WITHIN THE Linear

STANDARD ACCURACY (CURRENTLY 0.1 PER-CENT). IN ORDER TO USE THE Linear

STANDARD ACCURACY YOU NEED NOT SPECIFY ANY ERROR LAW AT ALL. IN Linear

THIS CASE INCLUDE THE HOLLERITH SECTION, MF=1, MT=451, FOR EACH Linear

MATERIAL. Linear

Linear

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Linear

THEN USE STANDARD FILENAMES. Linear

Linear

IN THIS CASE THE FOLLOWING 9 INPUT LINES ARE REQUIRED Linear

Linear

1 0 1.00000- 6 0 Linear

(USE DEFAULT FILENAME = ENDFB.IN) Linear

(USE DEFAULT FILENAME = ENDFB.OUT) Linear

92000 1451 92999 1451 Linear

92000 3 0 92999 3999 Linear

90232 1451 0 1451 Linear

90232 3 0 0 3 0 (UPPER LIMIT AUTOMATICALLY SET TO 90232 3999) Linear

(END OF REQUEST LIST) Linear

(0.1 PER-CENT ERROR, END OF ERROR LAW) Linear

Linear

EXAMPLE INPUT NO. 3 Linear

------------------- Linear

LINEARIZE ALL MATERIALS ON AN ENDF/B TAPE TO WITHIN AN ACCURACY Linear

OF 0.5 PER-CENT (0.005 AS A FRACTION). IN THIS CASE YOU NEED NOT Linear

SPECIFY THE MAT, MF, MT RANGES. Linear

Linear

READ THE ENDF/B DATA FROM \ENDFB6\ZA092238 AND WRITE THE ENDF/B Linear

DATA TO \ENDFB6\LINEAR\ZA092238. Linear

Linear

IN THIS CASE THE FOLLOWING 6 INPUT LINES ARE REQUIRED Linear

Linear

(MAT, 1.0E-10 BARNS, THIN) Linear

\ENDFB6\ZA092238 Linear

\ENDFB6\LINEAR\ZA092238 Linear

(RETRIEVE ALL DATA, END REQUEST LIST) Linear

5.00000-03 Linear

(END OF ERROR LAW) Linear

Linear

NOTE THAT IN THIS CASE IF THE INPUT HAD SPECIFIED AN EQUIVALENT Linear

ENERGY DEPENDENT ERROR LAW BY GIVING A NUMBER OF ENERGY POINTS Linear

AT EACH OF WHICH THE ERROR IS 0.5 PER-CENT THE PROGRAM WOULD TAKE Linear

LONGER TO RUN (I.E., ONLY USE AN ENERGY DEPENDENT ERROR LAW WHEN Linear

IT IS NECESSARY). Linear

Linear

EXAMPLE INPUT NO. 4 Linear

------------------- Linear

IN ORDER TO LINEARIZE ALL MATERIALS ON AN ENDF/B TAPE TO THE Linear

STANDARD OPTION OF 0.1 PER-CENT IT IS ADEQUATE TO INPUT A SET Linear

OF COMPLETELY BLANK LINES WHICH WILL AUTOMATICALLY INVOKE ALL Linear

OF THE STANDARD OPTIONS. Linear

Linear

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Linear

THEN USE STANDARD FILENAMES. Linear

Linear

IN THIS CASE THE FOLLOWING THREE INPUT LINES ARE REQUIRED Linear

Linear

(MAT, 1.0E-10 BARNS, THIN) Linear

(USE DEFAULT FILENAME = ENDFB.IN) Linear

(USE DEFAULT FILENAME = ENDFB.OUT) Linear

(RETRIEVE ALL DATA, END REQUEST LIST) Linear

(0.1 PER-CENT ERROR, END OF ERROR LAW) Linear

Linear

======================================================================= Linear

======================================================================= Merger

Merger

PROGRAM MERGER Merger

VERSION 80-1 (JANUARY 1980) Merger

VERSION 80-2 (DECEMBER 1980) Merger

VERSION 82-1 (JANUARY 1982) Merger

VERSION 83-1 (JANUARY 1983)*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Merger

VERSION 85-1 (AUGUST 1985) *FORTRAN-77/H VERSION Merger

VERSION 86-1 (JANUARY 1986)*ENDF/B-VI FORMATS Merger

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Merger

FILE NAMES (SEE, SUBROUTINES FILIO1 Merger

AND FILIO2 FOR DETAILS). Merger

*IMPROVED BASED ON USER COMMENTS. Merger

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Merger

INSURE PROGRAM WILL NOT DO ANYTHING Merger

CRAZY. Merger

*UPDATED TO USE NEW PROGRAM CONVERT Merger

KEYWORDS. Merger

*ADDED LIVERMORE CIVIC COMPILER Merger

CONVENTIONS. Merger

VERSION 92-1 (JANUARY 1992)*UPDATED BASED ON USER COMMENTS Merger

*ADDED FORTRAN SAVE OPTION Merger

VERSION 92-2 (JULY 1992) *ALLOW UP TO 99 ENDF/B DATA FILES. Merger

(TO ALLOW MANAGEMENT OF THE ENTIRE Merger

ENDF/B SYSTEM). Merger

VERSION 94-1 (JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES Merger

TO ALLOW ACCESS TO FILE STRUCTURES Merger

(WARNING - INPUT PARAMETER FORMAT Merger

HAS BEEN CHANGED) Merger

*ONLY SPECIFY FILENAMES - NO UNIT Merger

NUMBERS ON INPUT (WARNING - INPUT Merger

PARAMETERS FORMAT HAS BEEN CHANGED) Merger

*CLOSE ALL FILES BEFORE TERMINATING Merger

(SEE, SUBROUTINE ENDIT) Merger

*REQUEST LOG DELETED Merger

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Merger

*IMPROVED COMPUTER INDEPENDENCE Merger

*ALL DOUBLE PRECISION Merger

*ON SCREEN OUTPUT Merger

*UNIFORM TREATMENT OF ENDF/B I/O Merger

*IMPROVED OUTPUT PRECISION Merger

VERSION 99-1 (MARCH 1999) *GENERAL IMPROVEMENTS BASED ON Merger

USER FEEDBACK Merger

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Merger

USER FEEDBACK Merger

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Merger

VERS. 2004-1 (MERCH 2004) *ADDED INCLUDE TO DEFINE COMMON Merger

*ADDED TEND LINE IF NO DATA RETRIEVED Merger

Merger

OWNED, MAINTAINED AND DISTRIBUTED BY Merger

------------------------------------ Merger

THE NUCLEAR DATA SECTION Merger

INTERNATIONAL ATOMIC ENERGY AGENCY Merger

P.O. BOX 100 Merger

A-1400, VIENNA, AUSTRIA Merger

EUROPE Merger

Merger

ORIGINALLY WRITTEN BY Merger

------------------------------------ Merger

DERMOTT E. CULLEN Merger

UNIVERSITY OF CALIFORNIA Merger

LAWRENCE LIVERMORE NATIONAL LABORATORY Merger

L-159 Merger

P.O. BOX 808 Merger

LIVERMORE, CA 94550 Merger

U.S.A. Merger

TELEPHONE 925-423-7359 Merger

E. MAIL CULLEN1@LLNL.GOV Merger

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Merger

Merger

AUTHORS MESSAGE Merger

--------------- Merger

THE COMMENTS BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION Merger

FOR THIS PROGRAM INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ Merger

ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY THE Merger

COMMENTS CONCERNING MACHINE DEPENDENT CODING. Merger

Merger

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Merger

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Merger

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Merger

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Merger

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Merger

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Merger

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Merger

COMPUTER. Merger

Merger

PURPOSE Merger

------- Merger

THIS PROGRAM IS DESIGNED TO SELECTIVELY RETRIEVE DATA OFF OF FROM Merger

1 TO 10 ENDF/B DATA TAPES AND TO MERGE THE SELECTED DATA INTO A Merger

SINGLE MAT/MF/MT ORDERED FINAL OUTPUT FILE. Merger

Merger

IN THE DISCUSSION THAT FOLLOWS FOR SIMPLICITY THE ENDF/B Merger

TERMINOLOGY---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL Merger

MEDIUM USED MAY BE TAPE, CARD, DISK OR ANY OTHER MEDIUM. Merger

Merger

ENDF/B FORMAT Merger

------------- Merger

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Merger

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Merger

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV OR V FORMAT). Merger

Merger

THE ONLY NUMERICAL DATA THAT THIS PROGRAM READS IS THE ZA FROM THE Merger

FIRST CARD OF EACH SECTION AND THE MAT/MF/MT FROM EACH CARD. Merger

SEQUENCE NUMBERS ARE IGNORED ON INPUT AND ALL OTHER FIELDS ARE Merger

READ AS HOLLERITH. AS SUCH THIS PROGRAM NEED NOT DISTINGUISH Merger

BETWEEN DIFFERENT VERSIONS OF THE ENDF/B FORMAT. Merger

Merger

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Merger

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Merger

ASSUMED THAT THE MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE Merger

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Merger

CORRECTLY OUTPUT ON ALL CARDS. Merger

Merger

SECTION SIZE Merger

------------ Merger

SINCE THIS PROGRAM ONLY READS THE DATA ONE CARD AT A TIME THERE Merger

IS NO LIMIT TO THE SIZE OF ANY GIVEN SECTION, E.G. THE TOTAL Merger

CROSS SECTION MAY BE DESCRIBED BY 200,000 DATA POINTS. Merger

Merger

SELECTION OF DATA Merger

----------------- Merger

THE USER MAY CHOOSE TO MERGE ALL DATA OR THE USER MAY SPECIFY Merger

THAT ONLY CERTAIN DATA SHOULD BE SELECTED. THE DATA TO BE Merger

SELECTED IS DEFINED BY SPECIFYING UP TO 100 MAT/MF/MT OR Merger

ZA/MF/MT RANGES. EACH RANGE IS DEFINED BY LOWER AND UPPER LIMITS Merger

OF MAT/MF/MT OR ZA/MF/MT. Merger

Merger

REQUEST LIMITS Merger

-------------- Merger

IN ORDER TO SIMPLIFY THE INPUT OF SELECTION REQUESTS THE FOLLOWING Merger

CONVENTIONS HAVE BEEN INTRODUCED IN ORDER TO DEFINE THE UPPER Merger

LIMITS OF REQUESTS IF THEY ARE NOT DEFINED BY INPUT (I.E., IF THEY Merger

ARE ZERO). Merger

Merger

(1) MAT OR ZA - IF THE UPPER LIMIT IS ZERO IT IS SET EQUAL TO THE Merger

LOWER LIMIT. Merger

(2) MF OR MT - IF THE UPPER LIMIT IS ZERO IT IS SET EQUAL TO THE Merger

MAXIMUM POSSIBLE VALUE, 99 OR 999 RESPECTIVELY. Merger

Merger

WITH THESE CONVENTIONS AN ENTIRE EVALUATION MAY BE SELECTED BY Merger

MERELY SPECIFYING THE LOWER LIMIT OF MAT OR ZA. THE UPPER MAT OR Merger

ZA LIMIT WILL BE SET EQUAL TO THE LOWER LIMIT, THE LOWER LIMITS OF Merger

MF/MT WILL BE 0/0 AND THE UPPER LIMITS OF MF/MT WILL BE SET TO Merger

99/999. THIS WILL CAUSE ALL SECTIONS OF A SINGLE EVALUATION TO BE Merger

SELECTED. Merger

Merger

SATISFYING SELECTION CRITERIA Merger

----------------------------- Merger

IN ORDER FOR A SECTION TO MEET THE SELECTION CRITERIA SPECIFIED Merger

BY ONE OF THE RETRIEVAL REQUESTS, EACH OF THE THREE FIELDS ( Merger

MAT/MF/MT OR ZA/MF/MT) MUST INDIVIDUALLY SATISFY THE CORRESPONDING Merger

LIMITS OF THE REQUEST. IT IS NOT SUFFICIENT THAT THE MAT OF A Merger

SECTION LIE BETWEEN THE MINIMUM AND MAXIMUM MATS OF A REQUEST. THE Merger

MF AND MT WILL ALSO BE INDIVIDUALLY COMPARED TO THE MF AND MT Merger

LIMITS OF THE REQUEST. FOR EXAMPLE, A SECTION WITH MAT/MF/MT= Merger

2500/3/2 DOES NOT SATISFY A REQUEST THAT SPECIFIES A REQUEST USING Merger

THE RANGE 2000/3/1 THROUGH 3000/3/1. THIS REQUEST SPECIFIES ALL Merger

MATERIALS WITH MAT BETWEEN 2000 AND 3000, BUT ONLY THOSE SECTIONS Merger

WITH MF/MT=3/1. SIMILARLY A REQUEST FOR 2000/3/1 THROUGH 3000/99/ Merger

999 WILL NOT SELECT ANY SECTIONS WITH MF=1 OR 2, SINCE THE Merger

REQUEST SPECIFIES ALL MATERIALS WITH MAT BETWEEN 2000 AND 3000, Merger

BUT ONLY THOSE SECTIONS WITH MF= 3, OR MORE. Merger

Merger

DUPLICATE SECTIONS Merger

------------------ Merger

IF TWO OR MORE SECTIONS WITH THE SAME MAT/MF/MT ARE FOUND EITHER Merger

ON THE SAME OR DIFFERENT TAPES, THE SECTION FROM THE TAPE DEFINED Merger

EARLIEST IN THE INPUT CARDS WILL BE COPIED TO THE FINAL TAPE AND Merger

ALL OTHER SECTIONS WITH THE SAME MAT/MF/MT WILL BE SKIPPED. THE Merger

OUTPUT REPORT WILL INDICATE WHICH SECTIONS WERE COPIED FROM WHICH Merger

TAPES, AS WELL AS WHICH SECTIONS ARE DUPLICATE AND WERE SKIPPED. Merger

Merger

REACTION INDEX Merger

-------------- Merger

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Merger

FOR EACH MATERIAL THE PROGRAM WILL FOLLOW THE CONVENTIONS Merger

DEFINED ABOVE AND ONLY COPY ONE SECTION MF=1, MT=451 AND SKIP Merger

ALL OTHERS (IF MORE THAN ONE). THIS CONVENTION HAS BEEN ADOPTED Merger

BECAUSE MOST USERS DO NOT REQUIRE A CORRECT REACTION INDEX FOR Merger

THERE APPLICATIONS AND IT WAS NOT CONSIDERED WORTHWHILE TO INCLUDE Merger

THE OVERHEAD OF CONSTRUCTING A CORRECT REACTION INDEX IN THIS Merger

PROGRAM. HOWEVER, IF YOU REQUIRE A REACTION INDEX FOR YOUR Merger

APPLICATION AFTER RUNNING THIS PROGRAM YOU MAY USE PROGRAM Merger

DICTIN TO CREATE ONE. Merger

Merger

RETRIEVAL STATISTICS Merger

-------------------- Merger

THERE WILL ALWAYS BE AN OUTPUT REPORT LISTING INDICATING WHICH Merger

SECTIONS WHERE SELECTED, WHICH DUPLICATE SECTIONS WERE SKIPPED, Merger

WHICH TAPE THE SECTION WAS ON, WHICH REQUEST (MAT/MF/MT OR Merger

ZA/MF/MT RANGE) CAUSED THE SECTION TO BE SELECTED AND HOW MANY Merger

CARDS WERE IN THE SECTION. IN ADDITION THE USER MAY OPTIONALLY Merger

OBTAIN A FILE CONTAINING THE SAME INFORMATION. THIS FILE MAY BE Merger

COMBINED WITH OTHER SIMILAR FILES OUTPUT BY THIS PROGRAM IN ORDER Merger

TO ACCUMULATE RETRIEVAL STATISTICS OVER A PERIOD OF TIME. IF Merger

SPECIFIED THIS FILE WILL CONTAIN THE FOLLOWING INFORMATION IN Merger

6I7 FORMAT. Merger

Merger

(1) ZA Merger

(2) MAT Merger

(3) MF Merger

(4) MT Merger

(5) NUMBER OF CARDS IN SECTION Merger

(6) REQUEST NUMBER THAT CAUSED SECTION TO BE SELECTED Merger

Merger

INPUT FILES Merger

----------- Merger

UNIT DESCRIPTION Merger

---- ----------- Merger

2 INPUT CARDS (BCD - 80 CHARACTERS/RECORD) Merger

VARY FROM 1 TO 99 ENDF/B DATA FILES (BCD - 80 CHARACTERS/RECORD) Merger

Merger

OUTPUT FILES Merger

------------ Merger

UNIT DESCRIPTION Merger

---- ----------- Merger

3 OUTPUT REPORT LISTING (BCD - 120 CHARACTERS/RECORD) Merger

10 MERGED ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Merger

Merger

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2) Merger

---------------------------------------------------------------- Merger

UNIT FILE NAME DESCRIPTION Merger

---- ---------- ----------- Merger

2 MERGER.INP INPUT PARAMETERS Merger

3 MERGER.LST OUTPUT LISTING Merger

11 ENDFB.OUT RETRIEVED ENDF/B DATA Merger

12 ENDFB.IN1 ENDF/B DATA TO READ...FILENAMES WILL BE DEFINED Merger

13 ENDFB.IN2 IN THE ORDER ENDFB.IN1, ENDFB.IN2,...ENDFB.I99 Merger

14 ENDFB.IN3 CORRESPONDING TO THE FIRST, SECOND,...99-TH Merger

15 ENDFB.IN4 ENDF/B DATA FILE TO READ. Merger

16 ENDFB.IN5 Merger

17 ENDFB.IN6 Merger

18 ENDFB.IN7 Merger

. Merger

. Merger

110 ENDFB.I99 Merger

Merger

INPUT CARDS Merger

----------- Merger

CARD COLUMNS FORMAT DESCRIPTION Merger

---- ------- ------ ----------- Merger

1 1-60 A60 FILENAME FOR MERGED OUTPUT. Merger

(LEAVE BLANK FOR STANDARD = ENDFB.OUT) Merger

2 1-66 16A4,A2 MERGED FILE LABEL Merger

IF BLANK - LABEL FROM FIRST FILE READ WILL Merger

BE OUTPUT Merger

67-70 I4 MERGED FILE ENDF/B NUMBER Merger

IF ZERO - NUMBER OF FIRST FILE READ WILL Merger

BE OUTPUT. Merger

71-72 I2 RETRIEVAL CRITERIA Merger

= 0 - MAT/MF/MT RANGES Merger

= 1 - ZA/MF/MT RANGES Merger

3-N 1-60 A60 FILENAME FOR FILE TO RETRIEVE DATA FROM Merger

(LEAVE BLANK FOR STANDARD..ENDFB.IN1,ETC.) Merger

TERMINATE LIST OF FILES WITH A LINE THAT Merger

SAYS END OR end Merger

VARY 1- 6 I6 LOWER PRIMARY LIMIT (MAT OR ZA) Merger

7- 8 I2 LOWER MF LIMIT Merger

9-11 I3 LOWER MT LIMIT Merger

12-17 I6 UPPER PRIMARY LIMIT (MAT OR ZA) Merger

18-19 I2 UPPER MF LIMIT Merger

20-22 I3 UPPER MT LIMIT Merger

RANGES OF MAT/MF/MT OR ZA/MF/MT TO BE Merger

RETRIEVED ARE SPECIFIED BY DEFINING Merger

ONE RANGE (LOWER AND UPPER LIMITS) PER Merger

CARD. THE USER MAY SPECIFY 0 TO 100 Merger

RANGES AND THE LIST OF REQUEST RANGES Merger

IS TERMINATED BY A BLANK CARD. IF Merger

THE FIRST CARD IS BLANK (0 REQUESTS) Merger

ALL DATA WILL BE RETRIEVED. IF THE UPPER Merger

PRIMARY CRITERIA (MAT OR ZA) IS LESS THAN Merger

THE LOWER PRIMARY CRITERIA, THE UPPER Merger

PRIMARY CRITERIA WILL BE SET EQUAL TO Merger

THE LOWER PRIMARY CRITERIA. IF THE UPPER Merger

MF OR MT LIMIT IS ZERO, OR BLANK, IT Merger

WILL BE SET TO THE MAXIMUM POSSIBLE Merger

VALUE, I.E. MF=99 OR MT=999 (SEE Merger

EXAMPLE INPUT). Merger

Merger

EXAMPLE INPUT NO. 1 Merger

------------------- Merger

MERGE ENDF/B DATA ONTO UNIT 10 FROM UNITS 11, 12, 13 AND 14. Merger

RETRIEVE DATA BY MAT NUMBER. RETRIEVE MATS 1103, 1106, ALL MATS Merger

BETWEEN 1204 AND 1215, MF=1, 3, 4 AND 5 OF MAT 1219 AND MF=3, Merger

MT=1 OF MAT 1304. USE STANDARD FILENAMES. Merger

Merger

THE FOLLOWING 13 INPUT CARDS ARE REQUIRED. Merger

Merger

ENDFB.OUT Merger

EXAMPLE FILE LABEL FOR MERGER 0 0 Merger

ENDFB.IN1 Merger

ENDFB.IN2 Merger

ENDFB.IN3 Merger

ENDFB.IN4 Merger

END Merger

1103 4317 (UPPER LIMIT SET TO 1103/99/999) Merger

1106 4317 (UPPER LIMIT SET TO 1106/99/999) Merger

1204 1215 4317 (UPPER LIMIT SET TO 1215/99/999) Merger

1219 1 1219 1 4317 (UPPER LIMIT SET TO 1219/ 1/999) Merger

1219 3 1219 5 4317 (UPPER LIMIT SET TO 1219/ 5/999) Merger

1304 3 1 1304 3 1 4317 (UPPER LIMIT COMPLETELY DEFINED) Merger

(BLANK CARD TERMINATES REQUESTS) Merger

Merger

EXAMPLE INPUT NO. 2 Merger

------------------- Merger

THE SAME AS EXAMPLE 1, EXCEPT SPECIFY FILENAMES Merger

Merger

\ENDFB6\MERGED.LIB Merger

EXAMPLE FILE LABEL FOR MERGER 0 0 Merger

ENDFB6.PART1 Merger

ENDFB6.PART2 Merger

ENDFB6.PART3 Merger

ENDFB6.PART4 Merger

END Merger

1103 4317 (UPPER LIMIT SET TO 1103/99/999) Merger

1106 4317 (UPPER LIMIT SET TO 1106/99/999) Merger

1204 1215 4317 (UPPER LIMIT SET TO 1215/99/999) Merger

1219 1 1219 1 4317 (UPPER LIMIT SET TO 1219/ 1/999) Merger

1219 3 1219 5 4317 (UPPER LIMIT SET TO 1219/ 5/999) Merger

1304 3 1 1304 3 1 4317 (UPPER LIMIT COMPLETELY DEFINED) Merger

(BLANK CARD TERMINATES REQUESTS) Merger

Merger

======================================================================= Merger

======================================================================= Mixer

Mixer

PROGRAM MIXER Mixer

Mixer

VERSION 76-1 (NOVEMBER 1976) Mixer

VERSION 81-1 (APRIL 1981) *IBM VERSION Mixer

VERSION 82-1 (AUGUST 1982) *COMPUTER INDEPENDENT VERSION Mixer

VERSION 84-1 (JUNE 1984) *SPECIAL I/O ROUTINES TO GUARANTEE Mixer

ACCURACY OF ENERGY. Mixer

*DOUBLE PRECISION TREATMENT OF ENERGY Mixer

(REQUIRED FOR NARROW RESONANCES). Mixer

VERSION 86-1 (JANUARY 1986)*FORTRAN-77/H VERSION Mixer

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Mixer

FILE NAMES (SEE, SUBROUTINE FILIO1 Mixer

AND FILIO2 FOR DETAILS). Mixer

*IMPROVED BASED ON USER COMMENTS. Mixer

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Mixer

INSURE PROGRAM WILL NOT DO ANYTHING Mixer

CRAZY. Mixer

*UPDATED TO USE NEW PROGRAM CONVERT Mixer

KEYWORDS. Mixer

*ADDED LIVERMORE CIVIC COMPILER Mixer

CONVENTIONS. Mixer

VERSION 92-1 (JANUARY 1992)*UPDATED BASED ON USER COMMENTS Mixer

*ADDED PHOTON CROSS SECTIONS Mixer

*ADDED FORTRAN SAVE OPTION Mixer

*OUTPUT IN ENDF/B-VI FORMAT Mixer

*COMPLETELY CONSISTENT I/O ROUTINES - Mixer

TO MINIMIZE COMPUTER DEPENDENCE. Mixer

*NOTE, CHANGE IN INPUT PARAMETER Mixer

FORMAT. Mixer

VERSION 94-1 (JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES Mixer

TO ALLOW ACCESS TO FILE STRUCTURES Mixer

(WARNING - INPUT PARAMETER FORMAT Mixer

HAS BEEN CHANGED) Mixer

*CLOSE ALL FILES BEFORE TERMINATING Mixer

(SEE, SUBROUTINE ENDIT) Mixer

*INCREASED INCORE PAGE SIZE FROM Mixer

1002 TO 4008. Mixer

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Mixer

*IMPROVED COMPUTER INDEPENDENCE Mixer

*ALL DOUBLE PRECISION Mixer

*ON SCREEN OUTPUT Mixer

*UNIFORM TREATMENT OF ENDF/B I/O Mixer

*IMPROVED OUTPUT PRECISION Mixer

*DEFINED SCRATCH FILE NAMES Mixer

*INCREASED INCORE PAGE SIZE FROM Mixer

4008 TO 12000. Mixer

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Mixer

POINT READ FOR MORE DIGITS Mixer

*UPDATED TEST FOR ENDF/B FORMAT Mixer

VERSION BASED ON RECENT FORMAT CHANGE Mixer

*GENERAL IMPROVEMENTS BASED ON Mixer

USER FEEDBACK Mixer

VERSION 99-2 (JUNE 1999) *ASSUME ENDF/B-VI, NOT V, IF MISSING Mixer

MF=1, MT-451. Mixer

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Mixer

USER FEEDBACK Mixer

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Mixer

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Mixer

*INCREASED INCORE PAGE SIZE FROM Mixer

12000 TO 60000. Mixer

Mixer

OWNED, MAINTAINED AND DISTRIBUTED BY Mixer

------------------------------------ Mixer

THE NUCLEAR DATA SECTION Mixer

INTERNATIONAL ATOMIC ENERGY AGENCY Mixer

P.O. BOX 100 Mixer

A-1400, VIENNA, AUSTRIA Mixer

EUROPE Mixer

Mixer

ORIGINALLY WRITTEN BY Mixer

------------------------------------ Mixer

DERMOTT E. CULLEN Mixer

UNIVERSITY OF CALIFORNIA Mixer

LAWRENCE LIVERMORE NATIONAL LABORATORY Mixer

L-159 Mixer

P.O. BOX 808 Mixer

LIVERMORE, CA 94550 Mixer

U.S.A. Mixer

TELEPHONE 925-423-7359 Mixer

E. MAIL CULLEN1@LLNL.GOV Mixer

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Mixer

Mixer

PURPOSE Mixer

------- Mixer

THIS PROGRAM IS DESIGNED TO CALCULATE THE ENERGY DEPENDENT CROSS Mixer

SECTION FOR A COMPOSITE MIXTURE OF UP TO 10 DIFFERENT MATERIALS. Mixer

Mixer

THE PRESENT VERSION WILL ONLY CALCULATE THE CROSS SECTION FOR ONE Mixer

FINAL REACTION (ENDF/B SECTION), E.G. TOTAL CROSS SECTION, BUT NOT Mixer

ANY OTHER REACTION. Mixer

Mixer

NOTE, THIS PROGRAM WILL NOT COMBINE ALL REACTIONS FOR A MIXTURE Mixer

OF MATERIALS DURING A SINGLE RUN - ONLY ONE REACTION WILL BE Mixer

CREATED PER RUN. Mixer

Mixer

EVALUATED DATA FORMAT Mixer

--------------------- Mixer

THE CROSS SECTIONS ARE READ FROM THE ENDF/B FORMAT AND THE Mixer

COMPOSITE CROSS SECTION IS CONVERTED TO AN EQUIVALENT BARNS/ATOM Mixer

FORM AND OUTPUT IN THE ENDF/B FORMAT WITH AN EQUIVALENT ATOMIC Mixer

WEIGHT. THE USER MUST SPECIFY THE COMPOSITION BY GIVING THE ZA, Mixer

MT AND GRAMS/CC OF EACH CONSTITUENT. IN ADDITION THE USER MUST Mixer

IDENTIFY THE COMPOSITE CROSS SECTION BY SPECIFYING THE ZA, MAT Mixer

AND MT TO BE USED IN THE ENDF/B FORMATTED OUTPUT. Mixer

Mixer

SINCE ONLY THE CROSS SECTIONS IN FILE 3 AND 23 ARE USED, AND THE Mixer

FORMAT FOR FILE 3/23 IS THE SAME IN ALL VERSIONS ON ENDF/B, THIS Mixer

PROGRAM MAY BE USED WITH ANY VERSION OF ENDF/B DATA (I.E., Mixer

ENDF/B-I, II, III, IV, V OR VI). DURING A SINGLE RUN IT MAY EVEN Mixer

BE USED TO READ AND COMBINE EVALUATIONS WHICH ARE IN DIFFERENT Mixer

VERSIONS OF THE ENDF/B FORMAT. Mixer

Mixer

ENDF/B FORMATTED OUTPUT WILL BE IN THE ENDF/B-VI FORMAT REGARDLESS Mixer

OF THE FORMAT OF THE INPUT ENDF/B DATA. THIS WILL ONLY EFFECT THE Mixer

HOLLERITH SECTION (MF=1, MT=451). THE FORMAT OF CROSS SECTIONS Mixer

(MF=3) IS THE SAME IN ALL VERSION OF THE ENDF/B FORMAT. Mixer

Mixer

IN ORDER TO GUARANTEE PROPER OPERATION OF THIS PROGRAM THE DATA Mixer

MUST BE PROPERLY CODED IN THE ENDF/B FORMAT. NO ERROR CHECKING IS Mixer

PERFORMED. IT IS PARTICULARLY IMPORTANT THAT THE FOLLOWING DATA Mixer

BE CORRECT Mixer

Mixer

(1) ZA, MF, MT - MUST BE CORRECT IN ORDER TO ALLOW PROGRAM TO Mixer

SELECT THE APPROPRIATE SECTIONS TO BE COMBINED. Mixer

(2) AWRE - ATOMIC WEIGHT RATIO MUST BE CORRECT TO ALLOW PROGRAM Mixer

TO CONVERT THE USER SPECIFIED GRAMS/CC INTO ATOMS/CC FOR Mixer

PROPER ATOM RATIO MIXING. Mixer

(3) (ENERGIES, CROSS SECTIONS) - MUST BE CORRECT, LINEARLY Mixer

======== Mixer

INTERPOLABLE, IN ASCENDING ENERGY ORDER OF (E, BARNS). Mixer

============ Mixer

Mixer

TO CONVERT ENDF/B FORMATTED DATA TO THE REQUIRED INPUT FORM Mixer

THE FOLLOWING PROGRAMS MAY BE USED, Mixer

LINEAR - CONVERT TABULATED CROSS SECTIONS TO LINEARLY Mixer

INTERPOLABLE FORM. Mixer

RECENT - RECONSTRUCT RESONANCE CONTRIBUTION, ADD TO BACKGROUND Mixer

CROSS SECTION AND OUTPUT THE COMBINATION IN LINEARLY Mixer

INTERPOLABLE FORM. Mixer

SIGMA1 - DOPPLER BROADEN CROSS SECTIONS TO ANY TEMPERATURE AND Mixer

OUTPUT THE RESULT IN LINEARLY INTERPOLABLE FORM. Mixer

Mixer

DOCUMENTATION Mixer

------------- Mixer

THE FACT THAT THIS PROGRAM HAS COMBINED THE DATA IS DOCUMENTED Mixer

IN THE OUTPUT ENDF/B FORMAT IN THE HOLLERITH SECTION BY FIRST Mixer

IDENTIFYING THE VERSION OF THIS PROGRAM THAT WAS USED, IN THE FORM Mixer

Mixer

********************( PROGRAM MIXER 2004-1) ********************** Mixer

Mixer

THIS IS FOLLOWED BY THE TWO LINE IDENTIFICATION INPUT BY THE USER. Mixer

THIS IS FOLLOWED BY COMPOSITION INPUT BY THE USER. Mixer

Mixer

NEUTRON OR PHOTON DATA Mixer

---------------------- Mixer

THIS PROGRAM WILL ALLOW YOU TO PROCESS EITHER NEUTRON OR PHOTON Mixer

CROSS SECTIONS - BUT YOU CANNOT MIX THE TWO TYPES TOGETHER. BY Mixer

INPUT YOU CAN SPECIFY THE OUTPUT MF = 3 (NEUTRONS) OR 23 (PHOTONS) Mixer

WHATEVER TYPE YOU SPECIFIED FOR OUTPUT IS THE ONLY TYPE OF DATA Mixer

WHICH WILL BE PROCESSED BY THIS PROGRAM. Mixer

Mixer

DEFINING THE COMPOSITION Mixer

------------------------ Mixer

THE USER MAY SPECIFY UP TO 10 DIFFERENT SECTIONS OF DATA TO BE Mixer

COMBINED, EACH SECTION IDENTIFIED BY ZA AND MT NUMBER. THE Mixer

AMOUNT OF EACH MATERIAL IS SPECIFIED BY DEFINING THE NUMBER OF Mixer

GRAMS/CC OF EACH MATERIAL IN THE COMPOSITE MIXTURE. THIS CAN BE Mixer

DERIVED FROM THE VOLUME FRACTION SIMPLY BY MULTIPLYING THE STP Mixer

DENSITY OF EACH MATERIAL BY ITS VOLUME FRACTION. NOTE, DO NOT Mixer

INPUT ATOM FRACTIONS. Mixer

Mixer

THE LIST OF SECTIONS TO BE COMBINED MAY BE SPECIFIED IN ANY Mixer

ORDER, I.E. THEY NEED NOT BE IN ZA ORDER OR THE ORDER THAT THE Mixer

EVALUATED DATA APPEARS ON THE ENDF/B FORMATTED TAPE. Mixer

Mixer

IF ANY REQUESTED SECTION OF DATA IS NOT FOUND ON THE ORIGINAL Mixer

ENDF/B FORMATTED FILE, THE PROGRAM WILL PRINT A LIST OF THE Mixer

MISSING SECTIONS AND TERMINATE. IF ALL REQUESTED SECTIONS ARE Mixer

FOUND THE PROGRAM WILL PRODUCE A COMPOSITE SECTION USING THE Mixer

UNION OF ALL ENERGIES FOUND IN ANY SECTION. THE COMPOSITE SECTION Mixer

WILL NOT BE THINNED. Mixer

Mixer

PRIOR TO LATER USE IN ANY APPLICATION THE NUMBER OF ENERGY POINTS Mixer

IN THE COMPOSITE CROSS SECTION MAY BE MINIMIZED BY USING PROGRAM Mixer

LINEAR, UCRL-50400, VOL. 17, PART B TO THIN THE DATA. Mixer

Mixer

ONLY LINEARLY INTERPOLABLE DATA Mixer

------------------------------- Mixer

THE CROSS SECTIONS TO BE COMBINED MUST BE IN LINEARLY INTERPOLABLE Mixer

TABULATED FORM (I. E., FILE 3 OR 23, INTERPOLATION LAW 2). Mixer

Mixer

TO CONVERT TABULATED CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM Mixer

SEE, PROGRAM LINEAR, UCRL-50400, VOL. 17, PART A. Mixer

Mixer

TO CONVERT RESONANCE PARAMETERS TO LINEARLY INTERPOLABLE FORM SEE, Mixer

PROGRAM RECENT, UCRL-50400, VOL. 17, PART C. Mixer

Mixer

TO DOPPLER BROADEN LINEARLY INTERPOLABLE DATA TO ANY TEMPERATURE Mixer

SEE PROGRAM SIGMA1, UCRL-50400, VOL. 17, PART B. Mixer

Mixer

PAGING SYSTEM Mixer

------------- Mixer

THERE IS NO LIMIT TO THE THE NUMBER OF DATA POINTS IN EACH OF THE Mixer

SECTIONS TO BE COMBINED, NOR IS THERE A LIMIT TO THE NUMBER OF Mixer

DATA POINTS IN THE COMPOSITE MIXTURE CROSS SECTION. Mixer

Mixer

ALL REQUIRED SECTIONS OF DATA ARE READ FROM THE ORIGINAL ENDF/B Mixer

FORMATTED FILE. ANY SECTION OF 60000 OR FEWER POINTS WILL BE Mixer

TOTALLY CORE RESIDENT. LARGER SECTIONS ARE LOADED INTO A PAGING Mixer

SYSTEM USING A SCRATCH FILE WITH ONLY 60000 POINTS PER SECTION Mixer

CORE RESIDENT AT ANY ONE TIME. SIMILARLY THE COMPOSITE SECTION Mixer

WILL BE TOTALLY CORE RESIDENT IF IT CONTAINS 60000 OR FEWER POINTS Mixer

AND LARGER COMPOSITE SECTIONS WILL BE LOADED INTO A PAGING Mixer

SYSTEM WHERE ONLY 60000 POINTS ARE CORE RESIDENT AT ANY TIME. SINC Mixer

A PAGING SYSTEM MAY BE USED BY ANY SECTION OF DATA THERE IS NO Mixer

LIMIT TO THE SIZE OF EITHER THE ORIGINAL SECTIONS, NOR TO THE Mixer

COMPOSITE SECTION, E.G. A SECTION MAY CONTAIN 100,000 ENERGIES Mixer

AND CROSS SECTIONS TO DESCRIBE A GIVEN REACTION. Mixer

Mixer

PAGE SIZE Mixer

--------- Mixer

THE PAGE SIZE USED IN THIS PROGRAM IS DEFINED BY THE PARAMETER Mixer

NPAGE AND THE DIMENSIONS OF THE ARRAYS XTAB AND YTAB. IN ORDER Mixer

TO ADAPT THIS PROGRAM FOR USE ON ANY COMPUTER THE PAGE SIZE MAY Mixer

BE INCREASED OR DECREASED BUT THE FOLLOWING RULES MUST BE FOLLOWED Mixer

==== Mixer

Mixer

(1) NPAGE - MUST BE A MULTIPLE OF 3 IN ORDER TO ALLOW THE PROGRAM Mixer

TO READ FULL CARDS OF ENDF/B DATA (3 POINTS PER LINE). FAILURE Mixer

TO FOLLOW THIS RULE CAN LEAD TO LOSS OF DATA AND/OR PROGRAM Mixer

ERRORS DURING EXECUTION. Mixer

(3) YTAB - THE DIMENSION OF YTAB MUST BE (NPAGE,11). Mixer

(4) XTAB - THE DIMENSION OF XTAB MUST BE (NPAGE,11). Mixer

Mixer

DOPPLER BROADENING Mixer

------------------ Mixer

THE COMPOSITE CROSS SECTION OUTPUT FROM THIS PROGRAM SHOULD NOT Mixer

BE DOPPLER BROADENED USING PROGRAM SIGMA1, OR THE EQUIVALENT. THE Mixer

ATOMIC WEIGHT USED TO IDENTIFY THE COMPOSITE MIXTURE IS BASED ON Mixer

THE ATOM FRACTION OF EACH CONSTITUENT AND CANNOT BE USED TO Mixer

CHARACTERIZE THE BROADENING OF ANY GIVEN RESONANCE IN THE MIXTURE Mixer

DUE TO THE CONTRIBUTION OF ONE CONSTITUENT. IN ORDER TO CONSIDER Mixer

DOPPLER BROADENING FIRST USE PROGRAM SIGMA1 TO BROADEN THE CROSS Mixer

SECTION FOR EACH OF THE CONSTITUENTS AND THEN COMBINE THE Mixer

BROADENED DATA USING PROGRAM MIXER. Mixer

Mixer

EXAMPLE USE Mixer

----------- Mixer

THE OUTPUT FROM THIS PROGRAM HAS BEEN FOUND TO BE EXTREMELY Mixer

USEFUL IN THE FOLLOWING APPLICATIONS... Mixer

Mixer

(1) CALCULATE A COMPOSITE TOTAL CROSS SECTON FOR LATER USE AS Mixer

A WEIGHTING FUNCTION IN SELF-SHIELDING THE CROSS SECTIONS Mixer

OF EACH CONSTITUENT OF THE MIXTURE SEPARATELY. Mixer

Mixer

PROGRAM GROUPIE CAN USE THE CALCULATED COMPOSITE TOTAL CROSS Mixer

SECTION AS THE TOTAL CROSS SECTION FOR EACH CONSTITUENT OF Mixer

THE MIXTURE IN ORDER TO CALCULATE SELF-SHIELDED CROSS SECTION Mixer

FOR EACH CONSTITUENT OF THE MIXTURE. Mixer

Mixer

(2) CALCULATE COMPOSITE TOTAL AND FISSION CROSS SECTIONS IN Mixer

ORDER TO CALCULATE THE TRANSMISSION AND SELF-INDICATION Mixer

THROUGH COMPOSITE MATERIALS. GENERALLY IN THIS CASE THE Mixer

TOTAL CROSS SECTION WILL BE CALCULATED FOR THE COMPOSITION Mixer

OF THE SAMPLE AND THE FISSION CROSS SECTION WILL BE Mixer

CALCULATED FOR THE COMPOSITION OF THE FISSION CHAMBER Mixer

(WHICH GENERALLY WILL HAVE A DIFFERENT COMPOSITION THAN THE Mixer

SAMPLE). Mixer

Mixer

PROGRAM VIRGIN CAN USE THE OUTPUT FROM THIS PROGRAM TO Mixer

PERFORM TRANSMISSION AND SELF-INDICATION CALCULATIONS. Mixer

PROGRAM VIRGIN WILL ANALYTICALLY CALCULATE THE UNCOLLIDED Mixer

(I.E. VIRGIN) FLUX TRANSMITTED AND REACTION RATE DUE TO ANY Mixer

TABULATED LINEARLY INTERPOLABLE INCIDENT SPECTRUM. RESULTS Mixer

WILL BE PRESENTLY FOR UP TO 10 DIFFERENT SAMPLE THICKNESSES Mixer

AND BINNED INTO ENERGY GROUPS IN ORDER TO SIMULATE AN Mixer

EXPERIMENTAL MEASUREMENT. Mixer

Mixer

(3) THE OUTPUT FROM THIS PROGRAM IS VERY USEFUL TO PLOT IN ORDER Mixer

TO SEE THE IMPORTANCE OF SPECIFIC CROSS SECTION FEATURES IN Mixer

THE COMPOSITE CROSS SECTION. Mixer

Mixer

PROGRAM COMPLOT CAN BE USED TO PLOT THE OUTPUT FROM THIS Mixer

PROGRAM AND IF REQUIRED EXAMINE ANY PARTICULAR ENERGY RANGE Mixer

IN DETAIL. IN ORDER TO DO THIS THE (ZA, MT) EQUIVALENCE OPTION Mixer

OF PROGRAM COMPLOT SHOULD BE USED. TO COMPARE ANY CONSTITUENT Mixer

CROSS SECTION TO THE COMPOSITE CROSS SECTION THE INPUT TO Mixer

COMPLOT SHOULD EQUATE THE (ZA,MT) OF THE COMPOSITE TO THE Mixer

(ZA,MT) OF ONE CONSTITUENT AND THE MULTIPLIER INPUT TO Mixer

COMPLOT SHOULD BE THE ATOM FRACTION FOR THE CONSTITUENT (THE Mixer

ATOM FRACTIONS ARE DEFINED IN THE OUTPUT LISTING FROM PROGRAM Mixer

MIXER). Mixer

Mixer

INPUT FILES Mixer

----------- Mixer

UNIT DESCRIPTION Mixer

---- ----------- Mixer

2 INPUT CARDS (BCD - 80 CHARACTERS/RECORD) Mixer

10 ORIGINAL EVALUATED DATA IN ENDF/B FORMAT Mixer

(BCD - 80 CHARACTERS/RECORD) Mixer

Mixer

OUTPUT FILES Mixer

------------ Mixer

UNIT DESCRIPTION Mixer

---- ----------- Mixer

3 OUTPUT LISTING (BCD - 120 CHARACTERS/RECORD) Mixer

11 COMPOSITE EVALUATED DATA IN ENDF/B FORMAT Mixer

(BCD - 80 CHARACTERS/RECORD) Mixer

Mixer

SCRATCH FILES Mixer

------------- Mixer

UNIT DESCRIPTION Mixer

---- ----------- Mixer

12 SCRATCH FILE FOR EACH OF THE 10 SECTIONS WHICH Mixer

13 WILL BE ADDED TOGETHER TO DEFINE THE FINAL Mixer

. SECTION (BINARY - 60000 AND 480000 WORDS/RECORD) Mixer

. . Mixer

. . Mixer

20 . Mixer

21 . Mixer

22 SCRATCH FILE FOR COMBINED SECTION. Mixer

(BINARY - 2004 WORDS/RECORD) Mixer

Mixer

STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2) Mixer

---------------------------------------------------------------- Mixer

UNIT FILE NAME Mixer

---- ---------- Mixer

2 MIXER.INP Mixer

3 MIXER.LST Mixer

10 ENDFB.IN Mixer

11 ENDFB.OUT Mixer

12-22 (SCRATCH) Mixer

Mixer

INPUT CARDS Mixer

----------- Mixer

LINE COLS. FORMAT NAME DESCRIPTION Mixer

---- ----- ------ ------- ---------- Mixer

1-2 1-66 16A4,A2 TITLE TWO LINE TITLE DESCRIBING PROBLEM Mixer

(THIS TITLE IS USED TO IDENTIFY THE Mixer

OUTPUT LISTING AND IS ALSO WRITTEN Mixer

IN MF=1, MT=451 (HOLLERITH SECTION) Mixer

OF THE ENDF/B FORMATTED OUTPUT TO Mixer

IDENTIFY THE COMPOSITE MIXTURE). Mixer

3 1-60 ENDF/B INPUT DATA FILENAME Mixer

(STANDARD OPTION = ENDFB.IN) Mixer

4 1-60 ENDF/B OUTPUT DATA FILENAME Mixer

(STANDARD OPTION = ENDFB.OUT) Mixer

5 1-11 I11 IZAOUT ZA IDENTIFICATION FOR COMBINATION Mixer

5 12-17 I6 MATOUT MAT IDENTIFICATION FOR COMBINATION Mixer

5 18-19 I2 MFOUT MF IDENTIFICATION FOR COMBINATION Mixer

5 20-22 I3 MTOUT MT IDENTIFICATION FOR COMBINATION Mixer

6-N 1-11 I11 IZAGET ZA (1000*Z+A) OF MATERIAL Mixer

6-N 12-22 I11 MTGET MT OF REACTION Mixer

6-N 23-33 E11.4 DENSE DENSITY OF MATERIAL (GRAMS/CC) Mixer

Mixer

THE SIXTH LINE IS REPEATED FOR EACH SECTION (FROM 2 TO 10). Mixer

SINCE THE ENDF/B FORMATTED OUTPUT IS IN BARNS/ATOM FORM A MINIMUM Mixer

OF TWO SECTIONS MUST BE COMBINED (I.E., IF ONLY ONE SECTION IS Mixer

SPECIFIED THE OUTPUT WOULD BE IDENTICAL TO THE INPUT AND AS SUCH Mixer

THE PROGRAM WILL CONSIDER THIS TO BE AN ERROR AND NOT PERFORM THE Mixer

CALCULATION). THE LIST OF SECTIONS IS TERMINATED BY A BLANK LINE. Mixer

Mixer

THE LIST OF SECTIONS TO BE COMBINED MAY BE SPECIFIED IN ANY Mixer

ORDER, I.E. THEY NEED NOT BE IN ZA ORDER OR THE ORDER THAT THE Mixer

EVALUATED DATA APPEARS ON THE ENDF/B FORMATTED TAPE. Mixer

Mixer

EXAMPLE INPUT NO. 1 Mixer

------------------- Mixer

CREATE THE TOTAL CROSS SECTION (MT=1) FOR STAINLESS STEEL AND Mixer

IDENTIFY THE COMBINED MATERIAL WITH ZA=26800 AND MAT=4000, Mixer

THE COMPOSITION BY VOLUME OF THE STEEL WILL BE... Mixer

Mixer

THE DATA FROM \ENDFB6\K300\LIBRARY.DAT AND WRITE DATA TO Mixer

\MIXER\STEEL.DAT Mixer

Mixer

IRON - 74.8 PER-CENT Mixer

CHROMIUM - 16.0 Mixer

NICKEL - 6.0 Mixer

MANGANESE - 2.0 Mixer

SILICON - 1.0 Mixer

CARBON - 0.2 Mixer

Mixer

THE INPUT MUST SPECIFY THE COMPOSITION BY GRAMS/CC. THIS IS Mixer

DEFINED AS THE PRODUCT OF THE STANDARD DENSITY (GRAMS/CC) Mixer

TIMES THE VOLUME FRACTION. NOTE, DO NOT USE ATOM FRACTIONS. Mixer

FOR THIS EXAMPLE THE FOLLOWING 12 INPUT CARDS ARE REQUIRED.... Mixer

Mixer

STAINLESS STEEL. COMPOSITION BY PER-CENT VOLUME IS 74.8-IRON, Mixer

16-CHROME, 6-NICKEL, 2-MANGANESE, 1-SILICON, 0.2-CARBON Mixer

\ENDFB6\K300\LIBRARY.DAT Mixer

\MIXER\STEEL.DAT Mixer

26800 4000 3 1 Mixer

26000 1 5.88676 (NOTE, GRAMS/CC INPUT FOR EACH Mixer

24000 1 1.150448 CONSTITUENT, E.G. FOR IRON THE Mixer

28000 1 0.533928 STP DENSITY IS 7.87 GRAMS/CC. Mixer

25055 1 0.1486 THE INPUT VALUE OF 5.88676 IS Mixer

14000 1 0.0233 0.748 X 7.87,I.E. VOLUME Mixer

6012 1 0.0044958 FRACTION TIMES STP DENSITY). Mixer

(BLANK LINE TERMINATES INPUT LIST) Mixer

Mixer

EXAMPLE INPUT NO. 2 Mixer

------------------- Mixer

THE SAME EXAMPLE AS THE ABOVE PROBLEM, ONLY USE THE STANDARD Mixer

ENDF/B DATA FILENAMES - ENDFB.IN AND ENDFB.OUT (THIS CAN BE Mixer

DONE BY LEAVING THE THIRD AND FOURTH INPUT LINES BLANK). Mixer

FOR THIS EXAMPLE THE FOLLOWING 12 INPUT CARDS ARE REQUIRED.... Mixer

Mixer

STAINLESS STEEL. COMPOSITION BY PER-CENT VOLUME IS 74.8-IRON, Mixer

16-CHROME, 6-NICKEL, 2-MANGANESE, 1-SILICON, 0.2-CARBON Mixer

(NOTE - THIS LINE IS REALLY BLANK) Mixer

(NOTE - THIS LINE IS REALLY BLANK) Mixer

26800 4000 3 1 Mixer

26000 1 5.88676 (NOTE, GRAMS/CC INPUT FOR EACH Mixer

24000 1 1.150448 CONSTITUENT, E.G. FOR IRON THE Mixer

28000 1 0.533928 STP DENSITY IS 7.87 GRAMS/CC. Mixer

25055 1 0.1486 THE INPUT VALUE OF 5.88676 IS Mixer

14000 1 0.0233 0.748 X 7.87,I.E. VOLUME Mixer

6012 1 0.0044958 FRACTION TIMES STP DENSITY). Mixer

(BLANK LINE TERMINATES INPUT LIST) Mixer

Mixer

======================================================================= Mixer

======================================================================= Recent

Recent

PROGRAM RECENT Recent

VERSION 79-1 (OCTOBER 1979) CDC-7600 Recent

VERSION 80-1 (MAY 1980) IBM, CDC AND CRAY VERSION Recent

VERSION 80-2 (DECEMBER 1980) IMPROVED TREATMENT OF UNRESOLVED Recent

REGION TO COMPUTE ALL REACTIONS AT Recent

THE SAME TIME. Recent

VERSION 81-1 (MARCH 1981) IMPROVED BASED ON USER COMMENTS. Recent

VERSION 81-2 (AUGUST 1981) ADDED MONITOR MODE. ADDED SPEED OPTION Recent

TO BYPASS BACKWARDS THINNING IF FILE 3 Recent

ALLOWABLE ERROR = 0.0 (NOTE THIS OPTION Recent

WILL RESULT IN ALL TABULATED POINTS Recent

FROM THE EVALUATION BEING KEPT IN THE Recent

OUTPUT FROM THIS PROGRAM). Recent

VERSION 82-1 (JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY. Recent

VERSION 83-1 (JANUARY 1983)*MAJOR RE-DESIGN. Recent

*PAGE SIZES INCREASED. Recent

*ELIMINATED COMPUTER DEPENDENT CODING. Recent

*NEW, MORE COMPATIBLE I/O UNIT NUMBERS. Recent

*ADDED OPTION TO KEEP ALL RECONSTRUCTED Recent

AND BACKGROUND ENERGY POINTS. Recent

*ADDED STANDARD ALLOWABLE ERROR OPTIONS Recent

(CURRENTLY 0.1 PER-CENT RECONSTRUCTION Recent

AND 0.0 PER-CENT THINNING). Recent

VERSION 83-2 (OCTOBER 1983) IMPROVED BASED ON USER COMMENTS. Recent

VERSION 84-1 (JANUARY 1984) IMPROVED INTERVAL HALFING CONVERGENCE. Recent

VERSION 85-1 (APRIL 1985) *A BRAND NEW PROGRAM WHICH COMPLETELY Recent

SUPERCEDES ALL PREVIOUS VERSIONS OF Recent

THIS PROGRAM. Recent

*UPDATED FOR ENDF/B-VI FORMATS. Recent

*ADDED GENERAL REICH-MOORE FORMALISM Recent

(WITH TWO FISSION CHANNELS). Recent

*DECREASED RUNNING TIME. Recent

*SPECIAL I/O ROUTINES TO GUARANTEE Recent

ACCURACY OF ENERGY. Recent

*DOUBLE PRECISION TREATMENT OF ENERGY Recent

(REQUIRED FOR NARROW RESONANCES). Recent

VERSION 85-2 (AUGUST 1985) *FORTRAN-77/H VERSION Recent

VERSION 86-1 (JANUARY 1986)*ENERGY DEPENDENT SCATTERING RADIUS Recent

VERSION 86-2 (JUNE 1986) *IF FIRST CHANCE FISSION (MT=19) Recent

BACKGROUND IS PRESENT ADD RESONANCE Recent

CONTRIBUTION OF FISSION TO IT. Recent

VERSION 86-3 (OCTOBER 1986)*MULTI-LEVEL OR REICH-MOORE..CORRECT Recent

POTENTIAL SCATTERING CROSS SECTION FOR Recent

MISSING AND/OR FICTICIOUS (L,J) Recent

SEQUENCES. Recent

VERSION 87-1 (JANUARY 1987)*IMPROVED COMBINING FILE 2+3 Recent

VERSION 87-2 (MARCH 1987) *CORRECTED ADLER-ADLER CALCULATIONS. Recent

VERSION 88-1 (JULY 1988) *UPDATED REICH-MOORE ENDF/B-VI FORMAT Recent

TO BE THE SAME AS REICH-MOORE FORMAT Recent

IN EARLIER VERSIONS OF ENDF/B FORMAT. Recent

*CHECK FOR PRELIMINARY ENDF/B-VI Recent

REICH-MOORE FORMAT (NOW ABANDONED) Recent

AND TERMINATE EXECUTION IF DATA IS Recent

IN THIS FORMAT. Recent

*CALCULATE CHANNEL RADIUS OR SET IT Recent

EQUAL TO THE SCATTERING RADIUS. Recent

*IMPLEMENTED HYBRID R-FUNCTION WITH THE Recent

FOLLOWING RESTRICTIONS Recent

- ONLY INELASTIC COMPETITION (NO Recent

CHARGED PARTICLES) Recent

- NO TABULATED FILE 2 BACKGROUND Recent

- NO TABULATED OPTICAL MODEL PHASE Recent

SHIFT Recent

*PROGRAM EXIT IF GENERAL R-MATRIX IN Recent

THE EVALUATION (THIS FORMALISM WILL Recent

BE IMPLEMENTED ONLY AFTER THE AUTHOR Recent

RECEIVES REAL EVALUATIONS WHICH USE Recent

THIS FORMALISM...UNTIL THEN IT IS Recent

IMPOSSIBLE TO ADEQUATELY TEST THAT Recent

THE CODING FOR THIS FORMALISM IS Recent

CORRECT). Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 1002 TO 4008. Recent

*DOUBLE PRECISION RESONANCE REGION Recent

LIMITS. Recent

*FILE 2 AND FILE 3 ENERGIES WHICH ARE Recent

NEARLY EQUAL ARE TREATED AS EQUAL Recent

(I.E., SAME TO ABOUT 9 DIGITS). Recent

*CHECK FILE 3 BACKGROUND CROSS SECTIONS Recent

IN EDIT MODE. Recent

*OPTION...INTERNALLY DEFINE FILENAMES Recent

(SEE SUBROUTINE FILEIO FOR DETAILS). Recent

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Recent

INSURE PROGRAM WILL NOT DO ANYTHING Recent

CRAZY. Recent

*UPDATED TO USE NEW PROGRAM CONVERT Recent

KEYWORDS. Recent

*CORRECTED MULTILEVEL, REICH-MOORE AND Recent

HYBRID R-FUNCTION POTENTIAL SCATTER Recent

TO ACCOUNT FOR REPEATED J-VALUES FOR Recent

THE SAME TARGET SPIN AND L-VALUE. Recent

*ADDED LIVERMORE CIVIC COMPILER Recent

CONVENTIONS. Recent

*UPDATED TO USE NEW ENDF/B-VI Recent

CONVENTION TO ALLOW UNRESOLVED Recent

RESONANCE CONTRIBUTION TO ALREADY Recent

BE INCLUDED IN THE FILE 3 CROSS Recent

SECTIONS (INFINITELY DIULUTE Recent

CONTRIBUTION). Recent

VERSION 90-1 (JUNE 1990) *UPDATED BASED ON USER COMMENTS Recent

*ADDED FORTRAN SAVE OPTION Recent

*NEW MORE CONSISTENT ENERGY OUTPUT Recent

ROUTINE Recent

VERSION 91-1 (JULY 1991) *NEW UNIFORM TREATMENT OF ALL RESONANCE Recent

FORMALISMS (SEE, COMMENTS BELOW) Recent

*NEW REICH-MOORE ALGORITHM Recent

*MORE EXTENSIVE ERROR CHECKING AND Recent

ERROR MESSAGE EXPLANATIONS Recent

VERSION 92-1 (JANUARY 1992)*MAJOR RESTRUCTING TO IMPROVE ACCURACY Recent

AND COMPUTER INDEPENDENCE. Recent

*INCREASED ENERGY POINT PAGE SIZE FROM Recent

1002 TO 4008. Recent

*NO MORE THAN 2 ENERGY POINTS WHERE Recent

CROSS SECTION IS ZERO AT BEGINNING Recent

OF A SECTION FOR EACH REACTION,E.G., Recent

THRESHOLD FISSION. Recent

*PROCESS ONLY A PORTION OF RESONANCE Recent

REGION - SEE EXPLANATION BELOW Recent

*ALL ENERGIES INTERNALLY ROUNDED PRIOR Recent

TO CALCULATIONS. Recent

*COMPLETELY CONSISTENT I/O AND ROUNDING Recent

ROUTINES - TO MINIMIZE COMPUTER Recent

DEPENDENCE. Recent

VERSION 93-1 (MARCH 1993) *UPDATED REICH-MOORE TREATMENT TO USE Recent

L DEPENDENT SCATTERING RADIUS (APL) Recent

RATHER THAN SCATTERING RADIUS (AP) Recent

(SEE, ENDF/B-VI FORMATS AND Recent

PROCEDURES MANUAL, PAGE 2.6) Recent

*INCREASED PAGE SIZE FROM 4008 TO Recent

20040 DATA POINTS. Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 4008 TO 20040. Recent

VERSION 94-1 (JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES Recent

TO ALLOW ACCESS TO FILE STRUCTURES Recent

(WARNING - INPUT PARAMETER FORMAT Recent

HAS BEEN CHANGED). Recent

*CLOSE ALL FILES BEFORE TERMINATING Recent

(SEE, SUBROUTINE ENDIT) Recent

VERSION 94-2 (AUGUST 1994) *CORRECTED ADDJ FOR ENERGY DEPENDENT Recent

(TABULATED) SCATTERING RADIUS CASE. Recent

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Recent

*IMPROVED COMPUTER INDEPENDENCE Recent

*ALL DOUBLE PRECISION Recent

*ON SCREEN OUTPUT Recent

*UNIFORM TREATMENT OF ENDF/B I/O Recent

*IMPROVED OUTPUT PRECISION Recent

*ALWAYS INCLUDE THERMAL VALUE Recent

*DEFINED SCRATCH FILE NAMES Recent

VERSION 97-1 (APRIL 1997) *OPTIONAL MAKE NEGATIVE CROSS Recent

SECTION = 0 FOR OUTPUT Recent

*INCREASED PAGE SIZE FROM 20040 TO Recent

120000 DATA POINTS. Recent

*INCREASED MAXIMUM NUMBER OF RESONANCES Recent

FROM 20040 TO 120000. Recent

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Recent

POINT READ FOR MORE DIGITS Recent

*UPDATED TEST FOR ENDF/B FORMAT Recent

VERSION BASED ON RECENT FORMAT CHANGE Recent

*UPDATED CONSTANTS BASED ON CSEWG Recent

SUBCOMMITTEE RECOMMENDATIONS Recent

*GENERAL IMPROVEMENTS BASED ON Recent

USER FEEDBACK Recent

VERSION 99-2 (JUNE 1999) *IMPLEMENTED NEW REICH-MOORE FORMALISM Recent

TO ALLOW DEFINITION OF (L,J,S) FOR Recent

EACH SEQUENCE. Recent

*ASSUME ENDF/B-VI, NOT V, IF MISSING Recent

MF=1, MT-451. Recent

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Recent

USER FEEDBACK Recent

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Recent

(SEPT. 2002) *OUTPUT RESONANCE WITH 9 DIGITS Recent

*TO BE C AND C++ COMPATIBLE OUTPUT Recent

VERS. 2004-1 (JAN. 2004) *ADDED INCLUDE 'recent.h' Recent

*MADE ENDF/B-VII READY Recent

*UPDATED FOR NEW REICH-MOORE LRF=7 Recent

PARAMETERS WITH COMPETITION Recent

*ADDED COULOMB PENETRATION FACTORS FOR Recent

LRF=7 COMPETITIVE CHANNELS. Recent

*EXTENDED DEFINITIONS OF PENETRATION Recent

FACTOR, LEVEL SHIFT FACTOR, AND Recent

POTENTIAL SCATTERING PHASE SHIFT Recent

ABOVE L = 5 TO INFINITY. Recent

*ADDED QUICK CALCULATION - IF THE Recent

INPUT ALLOWABLE ERROR IS 1.0 OR MORE Recent

(100 % OR MORE) THERE IS NO ITERATION Recent

TO CONVERGENCE - CROSS SECTION ARE Recent

QUICKLY CALCULATED ONLY AT A FIXED Recent

SET OF ENERGY POINTS, BASED ON THE Recent

ENERGY AND WIDTH OF ALL RESONANCES. Recent

THIS CAN BE USED TO QUICKLY "SEE" Recent

NEW EVALUATIONS THAT MAY CONTAIN Recent

ERRORS, THAT WOULD OTHERWISE CAUSE Recent

THIS CODE TO RUN FOR AN EXCESSIVELY Recent

LONG TIME. Recent

Recent

OWNED, MAINTAINED AND DISTRIBUTED BY Recent

------------------------------------ Recent

THE NUCLEAR DATA SECTION Recent

INTERNATIONAL ATOMIC ENERGY AGENCY Recent

P.O. BOX 100 Recent

A-1400, VIENNA, AUSTRIA Recent

EUROPE Recent

Recent

ORIGINALLY WRITTEN BY Recent

------------------------------------ Recent

DERMOTT E. CULLEN Recent

UNIVERSITY OF CALIFORNIA Recent

LAWRENCE LIVERMORE NATIONAL LABORATORY Recent

L-159 Recent

P.O. BOX 808 Recent

LIVERMORE, CA 94550 Recent

U.S.A. Recent

TELEPHONE 925-423-7359 Recent

E. MAIL CULLEN1@LLNL.GOV Recent

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Recent

Recent

Acknowledgement (Version 2004-1) Recent

================================================================== Recent

The author thanks Nancy Larson, ORNL, for providing her SAMRML Recent

code for comparison to RECENT output for Reich-Moore evaluations, Recent

in particular to verify results for the new LFR=7 evaluations. I Recent

also thank her for providing guidance to help me understand and Recent

implement this new teatment for Reich-Moore parameters. Recent

Recent

ACKNOWLEDGEMENT (VERSION 92-1) Recent

================================================================== Recent

THE AUTHOR THANKS SOL PEARLSTEIN (BROOKHAVEN NATIONAL LAB) FOR Recent

SIGNIFICANTLY CONTRIBUTING TOWARD IMPROVING THE ACCURACY AND Recent

COMPUTER INDEPENDENCE OF THIS CODE - THANKS, SOL Recent

================================================================== Recent

Recent

AUTHORS MESSAGE Recent

================================================================== Recent

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Recent

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Recent

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Recent

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY Recent

THE COMMENTS CONCERNING MACHINE DEPENDENT CODING. Recent

Recent

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Recent

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Recent

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Recent

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Recent

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Recent

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Recent

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Recent

COMPUTER. Recent

Recent

PURPOSE Recent

================================================================== Recent

THIS PROGRAM IS DESIGNED TO RECONSTRUCT THE RESONANCE CONTRIBUTION Recent

TO THE CROSS SECTION IN LINEARLY INTERPOLABLE FORM, ADD IN ANY Recent

LINEARLY INTERPOLABLE BACKGROUND CROSS SECTION AND OUTPUT THE Recent

RESULT IN THE ENDF/B FORMAT. THE CROSS SECTIONS OUTPUT BY THIS Recent

PROGRAM WILL BE LINEARLY INTERPOLABLE OVER THE ENTIRE ENERGY RANGE Recent

Recent

THE RESONANCE CONTRIBUTION IS CALCULATED FOR TOTAL (MT=1), Recent

ELASTIC (MT=2), CAPTURE (MT=102) AND FISSION (MT=18), ADDED Recent

TO THE BACKGROUND (IF ANY) AND OUTPUT. IN ADDITION, IF THERE Recent

IS A FIRST CHANCE FISSION (MT=19) BACKGROUND PRESENT THE RESONANCE Recent

CONTRIBUTION OF FISSION WILL BE ADDED TO THE BACKGROUND AND Recent

OUTPUT. IF THERE IS NO FIRST CHANCE FISSION (MT=19) BACKGROUND Recent

PRESENT THE PROGRAM WILL NOT OUTPUT MT=19. Recent

Recent

IN THE FOLLOWING FOR SIMPLICITY THE ENDF/B TERMINOLOGY--ENDF/B Recent

TAPE--WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE TAPE, CARDS, Recent

DISK OR ANY OTHER MEDIUM. Recent

Recent

PROCESSING DATA IN THE ENDF/B-VI FORMAT Recent

================================================================== Recent

IT HAS NOW BEEN CONFIRMED (PRIVATE COMMUNICATION, CHARLES DUNFORD, Recent

APRIL, 1991) THAT THE PROPER PROCEDURE TO FOLLOW WHEN THERE ARE Recent

MISSING OR DUPLICATE J VALUES IS TO IN ALL CASES ADD A SEQUENCE Recent

WITH NO RESONANCES TO ACCOUNT FOR THE CONTRIBUTION OF THE SEQUENCE Recent

TO THE POTENTIAL SCATTERING CROSS SECTION. Recent

Recent

THIS IS THE PROCEDURE WHICH WAS FOLLOWED BY ALL VERSIONS OF RECENT Recent

SINCE 86-3 AND WILL CONTINUE TO BE THE PROCEDURE. Recent

Recent

INPUT ENDF/B FORMAT AND CONVENTIONS Recent

================================================================== Recent

ENDF/B FORMAT Recent

------------- Recent

THIS PROGRAM ONLY USES THE ENDF/B BCD OR LINE IMAGE FORMAT (AS Recent

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Recent

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Recent

Recent

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Recent

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Recent

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Recent

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Recent

CORRECTLY OUTPUT ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451 Recent

AND ALL SECTIONS OF MF=2 AND 3 MUST BE CORRECT. THE PROGRAM COPIES Recent

ALL OTHER SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE Recent

TO THE CORRECTNESS OR INCORRECTNESS OF ALL OTHER SECTIONS. Recent

Recent

ENDF/B FORMAT VERSION Recent

--------------------- Recent

THE FORMATS AND CONVENTIONS FOR READING AND INTERPRETING THE DATA Recent

VARIES FROM ONE VERSION OF ENDF/B TO THE NEXT. HOWEVER, IF THE Recent

HOLLERITH SECTION (MF=1, MT=451) IS PRESENT IT IS POSSIBLE FOR Recent

THIS PROGRAM TO DISTINGUISH BETWEEN DATA IN THE ENDF/B-IV, V AND Recent

VI FORMATS AND TO USE THE APPROPRIATE CONVENTIONS FOR EACH Recent

ENDF/B VERSION (SEE, SUBROUTINE FILE1 FOR A DESCRIPTION OF HOW Recent

THIS IS DONE). IF THE HOLLERITH SECTION IS NOT PRESENT THE Recent

PROGRAM WILL ASSUME THE DATA IS IN THE ENDF/B-VI FORMAT AND USE Recent

ALL CONVENTIONS APPROPRIATE TO ENDF/B-V. USERS ARE ENCOURAGED TO Recent

INSURE THAT THE HOLLERITH SECTION (MF=1, MT=451) IS PRESENT IN Recent

ALL EVALUATIONS. Recent

Recent

INPUT OF ENERGIES Recent

----------------- Recent

ALL ENERGIES ARE READ IN DOUBLE PRECISION (BY SPECIAL FORTRAN I/O Recent

ROUTINES) AND ARE TREATED IN DOUBLE PRECISION IN ALL CALCULATIONS. Recent

Recent

OUTPUT ENDF/B FORMAT AND CONVENTIONS Recent

================================================================== Recent

CONTENTS OF OUTPUT Recent

------------------ Recent

ENTIRE EVALUATIONS ARE OUTPUT, NOT JUST THE RECONSTRUCTED FILE Recent

3 CROSS SECTIONS, E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE Recent

ALSO INCLUDED. Recent

Recent

DOCUMENTATION Recent

------------- Recent

THE FACT THAT THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED Recent

BY THE ADDITION OF COMMENT CARDS AT THE END OF EACH HOLLERITH Recent

SECTION IN THE FORM Recent

Recent

***************** RECENT (VERSION 2004-1) *************** Recent

RESONANCE CONTRIBUTION RECONSTRUCTED TO WITHIN 0.100 PER-CENT Recent

COMBINED DATA NOT THINNED (ALL RESONANCE + BACKGROUND DATA KEPT) Recent

Recent

THE ORDER OF ALL SIMILAR COMMENTS (FROM LINEAR, SIGMA1 AND GROUPY) Recent

REPRESENTS A COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON Recent

THE DATA, INCLUDING WHICH VERSION OF EACH PROGRAM WAS USED. Recent

Recent

THESE COMMENT CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Recent

I.E., THIS PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Recent

OF THE HOLLERITH SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF Recent

EARLIER VERSIONS OF ENDF/B. BY READING AN EXISTING MF=1, MT=451 Recent

IT IS POSSIBLE FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF Recent

THE ENDF/B FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF Recent

MF=1, MT=451 PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO Recent

DETERMINE WHICH VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND Recent

AS SUCH IT IS IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT Recent

SHOULD BE USED TO CREATE A HOLLERITH SECTION. Recent

Recent

REACTION INDEX Recent

-------------- Recent

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Recent

SECTION MF=1, MT=451 OF EACH EVALUATION. Recent

Recent

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Recent

THIS CONVENTION HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT Recent

REQUIRE A CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Recent

NOT CONSIDERED WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING Recent

A CORRECT REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE Recent

A REACTION INDEX FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Recent

YOU MAY USE PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX. Recent

Recent

OUTPUT FORMAT OF ENERGIES Recent

------------------------- Recent

IN THIS VERSION OF RECENT ALL FILE 3 ENERGIES WILL BE OUTPUT IN Recent

F (INSTEAD OF E) FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN Recent

WITH UP TO 9 DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN Recent

OUTPUT OPTION. HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS Recent

OF ENERGIES WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6 DIGITS Recent

TO THE 9 DIGIT OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE Recent

TO USE THE 9 DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA Recent

JUST DUE TO TRANSLATION OF ENERGIES FROM THEIR INTERNAL (BINARY) Recent

REPRESENTATION TO THE ENDF/B FORMAT. Recent

Recent

ACCURACY OF ENERGY Recent

------------------ Recent

IN ORDER TO ALLOW ENERGIES TO BE ACCURATELY OUTPUT TO 9 DIGITS Recent

ON SHORT WORD LENGTH COMPUTERS (E.G. IBM) ALL ENERGIES AND Recent

ENERGY DEPENDENT TERMS ARE READ AND TREATED IN DOUBLE PRECISION. Recent

Recent

OUTPUT OF RESONANCE PARAMETERS Recent

------------------------------ Recent

A SPECIAL CONVENTION HAS BEEN INTRODUCED REGARDING RESONANCE Recent

PARAMETERS. IN ORDER TO ALLOW THE USER TO DOPPLER BROADEN AND/OR Recent

SELF-SHIELD CROSS SECTIONS THE RESONANCE PARAMETERS ARE ALSO Recent

INCLUDED IN THE OUTPUT WITH THE EVALUATION. IN ORDER TO AVOID THE Recent

POSSIBILITY OF ADDING THE RESONANCE CONTRIBUTION A SECOND TIME Recent

TWO CONVENTIONS HAVE BEEN ADOPTED TO INDICATE THAT THE RESONANCE Recent

CONTRIBUTION HAS ALREADY BEEN ADDED TO THE FILE 3 CROSS SECTIONS, Recent

Recent

(1) WHEN THE DATA IS PROCESSED BY THIS PROGRAM LRP (IN MF=1, Recent

MT=451) IS SET EQUAL TO 2. THIS IS A CONVENTION WHICH HAS BEEN Recent

ADOPTED AS A STANDARD CONVENTION IN ENDF/B-VI, BUT IS ONLY TO BE Recent

USED FOR PROCESSED DATA, AS OPPOSED TO THE ORIGINAL EVALUATIONS. Recent

IN EVALUATIONS WHICH CONTAIN MF=1, MT=451 LRP CAN BE USED TO Recent

DETERMINE IF THE MATERIAL HAS BEEN PROCESSED. Recent

Recent

(2) THE LRU FLAG IN EACH SECTION OF FILE 2 DATA IS CHANGED TO Recent

LRU=LRU+3. FOR EXAMPLE WHEN READING AN ENDF/B EVALUATION LRU=0 Recent

(NO RESONANCES), =1 (RESOLVED) OR =2 (UNRESOLVED) INDICATES THAT Recent

THE DATA IS IN THE ORIGINAL ENDF/B FORM. LRU=3 (NO RESONANCES), Recent

=4 (RESOLVED) OR =5 (UNRESOLVED) INDICATES THAT THE RESONANCE Recent

CONTRIBUTION HAS ALREADY BEEN ADDED TO THE FILE 3 DATA. THIS Recent

SECOND CONVENTION HAS BEEN ADOPTED AS INSURANCE THAT THE RESONANCE Recent

CONTRIBUTION WILL NOT BE ADDED TWICE, EVEN FOR EVALUATIONS WHICH Recent

DO NOT CONTAIN MF=1, MT=451 (EVALUATIONS WHICH CONTAIN MF=1, Recent

MT=451 ARE COVERED BY CONVENTION (1), DESCRIBED ABOVE). Recent

Recent

UNIFORM TREATMENT OF RESONANCE FORMALISMS Recent

================================================================== Recent

NORMALIZATION Recent

============= Recent

ALL OF THE RESONANCE FORMALISMS INCLUDE A FACTOR OF, Recent

Recent

PI*(FRACTIONAL ABUNDANCE)/(K**2) Recent

Recent

THIS FACTOR HAS BEEN REMOVED FROM THE CALCULATION OF EACH TYPE Recent

OF RESONANCE FORMALISM AND IS APPLIED AS A FINAL NORMALIZATION Recent

AFTER THE CALCULATION, ONLY ONE PLACE IN THIS PROGRAM. Recent

Recent

FOR SIMPLICITY THIS TERM IS NOT INCLUDED IN THE FOLLOWING Recent

DERIVATIONS - IN ALL CASES THE ACTUAL CROSS SECTION IS A PRODUCT Recent

OF THE ABOVE FACTOR TIMES THE RESULTS PRESENTED BELOW. Recent

Recent

SIMILARITIES Recent

============ Recent

FOR THE RESOLVED RESONANCE REGION, EXCEPT FOR SINGLE LEVEL BREIT Recent

WIGNER, PARAMETERS ALL OF THE FORMALISMS DEFINE THE CROSS SECTIONS Recent

IN AN EQUIVALENT FORM, Recent

Recent

TOTAL = 2*GJ*REAL(1 - U) Recent

= 2*GJ*(1 - REAL(U)) Recent

ELASTIC = GJ*(1 - U)**2 Recent

= GJ*((1 - 2*REAL(U)) + (REAL(U)**2 + IM(U)**2)) Recent

= 2*GJ*(1 - REAL(U)) - GJ*(1 - (REAL(U)**2 + IM(U)**2)) Recent

Recent

SINCE THE FIRST TERM IS THE TOTAL, THE SECOND TERM MUST BE Recent

ABSORPTION. SO WE FIND, Recent

Recent

ABSORPTION = GJ*(1 - (REAL(U)**2 + IM(U)**2)) Recent

Recent

IN ALL CASES U IS DEFINED IN THE FORM, Recent

Recent

U = EXP(-I*2*PS)*((1-X) - I*Y) Recent

Recent

WHERE (X) AND (Y) ARE RELATED TO THE SYMMETRIC AND ANTI-SYMMETRIC Recent

CONTRIBUTIONS OF THE RESONANCES, RESPECTIVELY. ONLY THE DEFINITION Recent

OF (X) AND (Y) WILL BE DIFFERENT FOR EACH RESONANCE FORMALISM. Recent

BELOW WE WILL SHOW THAT WHAT MIGHT APPEAR TO BE A STRANGE CHOICE Recent

OF DEFINITION OF THE SIGN OF (X) AND(Y) HAS BEEN SELECTED SO THAT Recent

FOR BREIT-WIGNER PARAMETERS (X) AND (Y) CORRESPOND EXACTLY TO THE Recent

SYMMETRIC AND ANTI-SYMMETRIC CONTRIBUTION OF THE RESONANCES. Recent

Recent

U = (COS(2*PS) - I*SIN(2*PS))*((1-X) - I*Y) Recent

= ((1-X)*COS(2*PS) - Y*SIN(2*PS)) Recent

=-I*((1-X)*SIN(2*PS) + Y*COS(2*PS)) Recent

Recent

REAL(U) = ((1-X)*COS(2*PS) - Y*SIN(2*PS)) Recent

IM(U) =-((1-X)*SIN(2*PS) + Y*COS(2*PS)) Recent

Recent

R(U)**2 =((1-X)*COS(2*PS))**2 + (Y*SIN(2*PS))**2 Recent

-2*(1-X)*Y*COS(2*PS)*SIN(2*PS) Recent

I(U)**2 =((1-X)*SIN(2*PS))**2 + (Y*COS(2*PS))**2 Recent

+2*(1-X)*Y*COS(2*PS)*SIN(2*PS) Recent

Recent

THE TERMS 2*(1-X)*Y*COS(2*PS)*SIN(2*PS) CANCEL AND UPON USING Recent

THE IDENTITY COS(2*PS)**2 + SIN(2*PS)**2 = 1, Recent

Recent

SUM = (1-X)**2 + (Y)**2 Recent

Recent

WE NOW HAVE ALL THE QUANTITIES THAT WE NEED TO DEFINE THE CROSS Recent

SECTIONS, Recent

Recent

ELASTIC Recent

======= Recent

ELASTIC =GJ*(1 - 2*REAL(U) + (REAL(U)**2 + IM(U)**2)) Recent

=GJ*(1 - 2*((1-X)*COS(2*PS)-Y*SIN(2*PS))+(1-X)**2+(Y)**2) Recent

Recent

THIS CAN BE WRITTEN AS A SUM OF 2 SQUARES, Recent

Recent

ELASTIC =GJ*(COS(2*PS) - (1-X))**2 + (SIN(2*PS) + Y)**2) Recent

Recent

=GJ*((COS(2*PS))**2 - 2*(1-X)*COS(2*PS) + (1-X)**2) + Recent

(SIN(2*PS))**2 + 2*Y*SIN(2*PS) + (Y)**2) Recent

Recent

AGAIN USING THE IDENTITY COS(2*PS)**2 + SIN(2*PS)**2 = 1, WE CAN Recent

SEE THAT THE DEFINITION AS THE SUM OF 2 SQUARES IS IDENTICAL TO Recent

THE PRECEDING DEFINITION OF THE ELASTIC. Recent

Recent

ELASTIC =GJ*(COS(2*PS) - (1-X))**2 + (SIN(2*PS) + Y)**2) Recent

=GJ*((COS(2*PS)-1) + X)**2 + (SIN(2*PS) + Y)**2) Recent

Recent

USING THE IDENTITY (1 - COS(2*PS))) = 2*SIN(PS)**2, WE OBTAIN Recent

THE FINAL FORM FOR THE ELASTIC, Recent

Recent

ELASTIC =GJ*(2*SIN(PS)**2 - X)**2 + (SIN(2*PS) + Y)**2) Recent

Recent

ABSORPTION Recent

========== Recent

ABSORPTION = GJ*(1 - (REAL(U)**2 + IM(U)**2)) Recent

= GJ*(1 - ((1-X)**2 + (Y)**2) Recent

= GJ*(1 - (1 - 2*X + (X)**2 + (Y)**2) Recent

= GJ*(2*X - (X)**2 + (Y)**2) Recent

Recent

SINCE PHYSICALLY THE ABSORPTION CANNOT BE NEGATIVE WE CAN SEE Recent

THAT (X) MUST BE POSITIVE AND 2*X MUST BE GREATER THAN Recent

(X)**2 + (Y)**2, FOR ALL OF THE FORMALISMS. Recent

Recent

TOTAL Recent

===== Recent

IN THIS PROGRAM THE TOTAL CROSS SECTION IS ALWAYS DEFINED TO BE Recent

THE SUM OF ITS PARTS - SO THE ABOVE DEFINITION IS NEVER EXPLICITLY Recent

USED. HOWEVER, WE CAN LEARN SOMETHING BY EXAMINING THE DEFINITION, Recent

Recent

TOTAL = 2*GJ*REAL(1 - U) Recent

= 2*GJ*(1 - (((1-X)*COS(2*PS) - Y*SIN(2*PS))) Recent

= 2*GJ*((1 - COS(2*PS))*(1-X) - (1-X) + Y*SIN(2*PS)) Recent

= 2*GJ*(2*SIN(PS)**2*(1-X) - (1-X) + Y*SIN(2*PS)) Recent

Recent

= 4*GJ*SIN(PS)**2 + Recent

2*GJ*((X-1) - 2*X*SIN(PS)**2 + Y*SIN(2*PS)) Recent

Recent

THE IMPORTANT POINT TO NOTE IS THAT THE DEFINITION OF THE TOTAL Recent

DOES NOT EXPLICITLY CONTAIN ANY DEPENDENCE ON X**2 AND Y**2 - Recent

THE LEVEL-LEVEL INTERFERENCE TERMS. Recent

Recent

THIS IMPLIES THAT IF A GIVEN SET OF RESONANCE PARAMETERS ARE USED Recent

WITH THIS DEFINITION THEY WILL PRODUCE EXACTLY THE SAME TOTAL Recent

CROSS SECTION - WHETHER WE CLAIM THE PARAMETERS HAVE BEEN Recent

PRODUCED USING A SINGLE OR MULTI-LEVEL FIT. THIS RESULT COULD Recent

BE VERY MISLEADING, IF THIS RESULT FOR THE TOTAL IS IMPLIED TO Recent

MEAN THAT ONE INTERPRETATION OR THE OTHER WILL NOT HAVE ANY Recent

EFFECT ON THE INDIVIDUAL CROSS SECTIONS. Recent

Recent

STARTING FROM EXACTLY THE SAME RESONANCE PARAMETERS, RELATIVE TO Recent

THE RESULTS OBTAINED USING THE SINGLE LEVEL FORMULA, MULTI-LEVEL Recent

RESULTS WILL TEND TO ALWAYS DECREASE THE ABSORPTION AND INCREASE Recent

THE ELASTIC. THIS CAN BE IMMEDIATELY SEEN FROM OUR GENERAL Recent

MULTI-LEVEL DEFINITION OF ABSORPTION, Recent

Recent

ABSORPTION =GJ*(2*X - ((X)**2 + (Y)**2)) Recent

Recent

THE SINGLE LEVEL ABSORPTION IS, Recent

Recent

ABSORPTION =GJ*(2*X) Recent

Recent

THE DIFFERENCE BETWEEN THE TWO IS -2*GJ*(X**2 + Y**2), SO THAT Recent

REGARDLESS OF HOW WE DEFINE (X) AND (Y) THE INCLUSION OF THIS Recent

TERM WILL ALWAYS DECREASE ABSORPTION. SINCE THE TOTAL CROSS Recent

SECTION IS THE SAME IN BOTH CASE, THIS MEANS THAT THE ELASTIC Recent

HAS BEEN INCREASED BY THIS AMOUNT. Recent

Recent

AGAIN, THESE RESULTS ARE BASED ON STARTING FROM EXACTLY THE SAME Recent

PARAMETERS - IN ANY ACTUAL CASE THE PARAMETERS BASED ON A SINGLE Recent

OR MULTI-LEVEL FIT WILL BE QUITE DIFFERENT - THE POINT THAT WE Recent

WANT TO STRESS HERE IS THAT YOU SHOULD NEVER USE PARAMETERS Recent

WHICH HAVE BEEN DEFINED BY A FIT USING ONE FORMALISM - IN THE Recent

EQUATIONS FOR A DIFFERENT FORMALISM - AND ASSUME THAT THE RESULTS Recent

WILL BE CONSISTENT - AND NEVER USE THE TOTAL CROSS SECTION TO Recent

SEE WHETHER OR NOT A SET OF SINGLE LEVEL PARAMETERS CAN BE USED Recent

WITH A MULTI-LEVEL FORMALISM. Recent

Recent

POTENTIAL CROSS SECTION Recent

======================= Recent

FAR FROM RESONANCES (X) AND (Y) WILL BE SMALL AND THE ELASTIC Recent

CROSS SECTION REDUCES TO, Recent

Recent

ELASTIC =GJ*(2*SIN(PS)**2)**2 + (SIN(2*PS))**2 Recent

=GJ*4*(SIN(PS)**4 + SIN(2*PS)**2 Recent

Recent

USING THE IDENTITY SIN(2*PS) = 2*SIN(PS)*COS(PS) Recent

Recent

=4*GJ*(SIN(PS)**4 + (SIN(PS)*COS(PS))**2) Recent

=4*GJ*SIN(PS)**2*(SIN(PS)**2 + COS(PS)**2) Recent

=4*GJ*SIN(PS)**2 Recent

Recent

WHICH IS THE POTENTIAL CROSS SECTION. NOTE THAT THIS RESULT IS Recent

INDEPENDENT OF THE FORMALISM USED, AS IT MUST PHYSICALLY BE, Recent

AND AS SUCH ALTHOUGH AS YET WE HAVE NOT DEFINED IT, WE CAN Recent

NOW SEE THAT IN ALL CASES (PS) MUST BE THE PHASE SHIFT AND FOR Recent

CONSISTENCY IT MUST BE DEFINED USING EXACTLY THE SAME DEFINITION Recent

IN ALL CASES. Recent

Recent

IN ADDITION SINCE PHYSICALLY FOR EACH L VALUE WE EXPECT TO OBTAIN Recent

A POTENTIAL CROSS SECTION, Recent

Recent

4*(2*L+1)*SIN(PS)**2 Recent

Recent

OBVIOUSLY FOR CONSISTENCY WE MUST HAVE, Recent

Recent

(2*L+1) = (SUM OVER J) GJ Recent

Recent

ONLY IN THIS CASE WILL THE RESULTS BE CONSISTENT - THIS POINT WILL Recent

BE DISCUSSED IN DETAIL BELOW. Recent

Recent

WHAT ARE THIS TERMS (X) AND (Y) Recent

=============================== Recent

(X) AND (Y) CAN BE EASILY IDENTIFIED BY CONSIDERING THE SINGLE Recent

AND MULTI-LEVEL BREIT WIGNER FORMALISMS. IN THESE CASES WE WILL Recent

FIND THAT, Recent

Recent

X = GAM(N)*GAM(T)/2/DEN Recent

Y = GAM(N)*(E-ER)/DEN Recent

DEN = ((E-ER)**2 + (GAM(T)/2)**2) Recent

Recent

EXTREME CARE HAS TO BE USED TO PROPERLY DEFINE (Y) SUCH THAT IT Recent

IS NEGATIVE FOR E LESS THAN ER AND POSITIVE FOR E GREATER THAN Recent

ER. I WILL MERELY MENTION THAT THE EQUATIONS FOR ALL FORMALISMS Recent

IN ENDF-102 DO NOT CONSISTENTLY USE (E - ER) - IN SOME CASES Recent

THIS IS WRITTEN AS (ER - E), WHICH CAN LEAD TO AN INCORRECT Recent

SIGN IN THE DEFINITION OF THE (Y) THAT WE REQUIRE. Recent

Recent

THE INTERFERENCE TERMS CAN BE WRITTEN IN TERMS OF, Recent

1) LEVEL-SELF INTERFERENCE = THE CONTRIBUTION OF EACH LEVEL Recent

INTERFERRING WITH ITSELF Recent

2) LEVEL-LEVEL INTERFERENCE = THE CONTRIBUTION OF EACH LEVEL Recent

INTERFERRRING WITH ALL OTHER LEVELS Recent

Recent

WE WILL REFER TO THESE TWO AS (L-S) AND (L-L), Recent

Recent

X**2 = (GAM(N)*(GAM(T)/2)**2/(DEN)**2 + (L-L) Recent

= (GAM(N)**2*((GAM(T)/2)**2)/(DEN)**2 + (L-L) Recent

Y**2 = (GAM(N))**2*((E-ER))**2/(DEN)**2 + (L-L) Recent

Recent

X**2+Y**2= GAM(N)**2*DEN/(DEN)**2 = GAM(N)**2/DEN + (L-L) Recent

Recent

TO SEE THE EFFECT OF INCLUDING MULTI-LEVEL INTERFERENCE WE CAN Recent

CONSIDER OUR GENERAL EXPRESSION FOR ABSORPTION, Recent

Recent

ABSORPTION =GJ*(2*X - ((X)**2 + (Y)**2)) Recent

Recent

AND NOTE THAT FOR BOTH SINGLE AND MULTI-LEVEL BREIT WIGNER THE Recent

ENDF-102 SAYS TO TREAT ABSORPTION IN A SINGLE LEVEL APPROXIMATION Recent

I.E., IGNORE LEVEL-LEVEL INTERFERENCE. IF ALL INTERFERENCE IS Recent

IGNORED THIS IS EQUIVALENT TO COMPLETELY IGNORING X**2 + Y**2 AND Recent

DEFINING, Recent

Recent

ABSORPTION =GJ*2*X Recent

=2*GJ*GAM(N)*GAM(T)/DEN Recent

Recent

WHICH IS INCORRECT - SINCE THIS SEEMS TO INDICATE EVERYTHING IS Recent

ABSORBED. IN ORDER TO OBTAIN THE CORRECT EXPRESSION WE CANNOT Recent

COMPLETELY IGNORE INTERFERENCE - WE CAN IGNORE LEVEL-LEVEL Recent

INTERFERENCE, BUT WE MUST INCLUDE LEVEL-SELF INTERFERENCE, Recent

Recent

X**2+Y**2= GAM(N)**2/DEN Recent

Recent

ABSORPTION =GJ*(2*X - ((X)**2 + (Y)**2)) Recent

=GJ*GAM(N)*(GAM(T)-GAM(N))/DEN Recent

=GJ*GAM(N)*GAM(A)/DEN Recent

Recent

SUMMARY Recent

======= Recent

AN IMPORTANT POINT TO NOTE IS THE DEFINITION OF (X) AND (Y) Recent

WHICH IN ALL CASES WILL CORRESPOND TO THE SYMMETRIC AND Recent

ANTI-SYMMETRIC CONTRIBUTION OF THE RESONANCES. IN PARTICULAR Recent

DEFINING (U) IN TERMS OF (1-X) INSTEAD OF (X) IS EXTREMELY Recent

IMPORTANT. NOTE, THAT THE DEFINITION OF THE ELASTIC AND Recent

ABSORPTION ONLY INVOLVE (X), NOT (1-X). FAR FROM RESONANCES Recent

(X) CAN BE EXTREMELY SMALL, THEREFORE (1-X) WILL BE VERY CLOSE Recent

TO (1). IF THE CALCULATION PROCEEDS BY FIRST CALCULATING (1-X) Recent

AND THEN DEFINING (X) BY SUBTRACTING (1), EXTREME ROUND-OFF Recent

PROBLEMS CAN RESULT. THESE PROBLEMS CAN BE AVOIDED BY IN ALL Recent

CASES DEFINING (X) DIRECTLY, WITHOUT ANY DIFFERENCES. Recent

Recent

IN EACH FORMALISM THE DEFINITION OF (X) AND (Y) MAY BE DIFFERENT Recent

BUT ONCE WE HAVE DEFINED (X) AND (Y) WE CAN IMMEDIATELY WRITE Recent

THE CROSS SECTIONS USING A UNIFORM DEFINITION, Recent

Recent

ELASTIC =GJ*(2*SIN(PS)**2 - X)**2 + (SIN(2*PS) + Y)**2) Recent

Recent

ABSORPTION =-GJ*(2*X + (X)**2 + (Y)**2) Recent

Recent

AND DEFINE THE TOTAL AS THE SUM OF THESE 2 PARTS. Recent

Recent

RELATIONSHIP TO SINGLE LEVEL Recent

============================ Recent

HOW DO THE SINGLE AND MULTI-LEVEL FORMALISMS COMPARE. TO SEE, Recent

STARTING FROM OUR GENERAL DEFINITION OF THE ELASTIC IN THE FORM, Recent

Recent

ELASTIC =GJ*(2*SIN(PS)**2 + X)**2 + (SIN(2*PS) + Y)**2) Recent

=GJ*(4*SIN(PS)**4 - 4*X*SIN(PS)**2 + X**2 Recent

+ SIN(2*PS)**2 + 2*Y*SIN(2*PS) + Y**2) Recent

Recent

=4*GJ*SIN(PS)**2 + Recent

GJ*(X**2 + Y**2 Recent

-4*X*SIN(PS)**2 Recent

+2*Y*SIN(2*PS)) Recent

Recent

AND OUR SPECIFIC DEFINITIONS OF (X) AND (Y) FOR MULTI-LEVEL BREIT- Recent

WIGNER PARAMETERS, Recent

Recent

X = GAM(N)*GAM(T)/2/DEN Recent

Y = GAM(N)*(E-ER)/DEN Recent

DEN = ((E-ER)**2 + (GAM(T)/2)**2) Recent

Recent

X**2+Y**2= GAM(N)**2/DEN + (L-L) Recent

Recent

WE CAN RECOGNIZE X**2 AND Y**2 AS THE INTERFERENCE - (L-S) + (L-L) Recent

TERMS IN THE MULTI-LEVEL FORMALISM. IN ORDER TO OBTAIN THE SINGLE Recent

LEVEL EQUATION WE CAN ASSUME THAT EACH LEVEL DOES NOT INTERFERE Recent

WITH ANY OTHER LEVEL - THEREFORE THE (L-L) CONTRIBUTION IS ZERO. Recent

Recent

ELASTIC =4*GJ*SIN(PS)**2 + Recent

GJ*GAM(N)*(GAM(N) Recent

-2*GAM(T)*SIN(PS)**2 Recent

+2*(E-ER)*SIN(2*PS))/DEN Recent

Recent

WHICH IS THE FORM THAT IT APPEARS IN ENDF-102, EXCEPT FOR TWO Recent

TYPOGRAPHICAL ERRORS IN THE SECOND TERM, Recent

Recent

-2*GAM(T)*SIN(PS)**2 Recent

Recent

WHICH IN ENDF-102 IS WRITTEN, Recent

Recent

-2*(GAM(T)-GAM(N))*SIN(2*PS)**2 Recent

Recent

PROGRAM CONVENTIONS Recent

================================================================== Recent

MINIMUM INPUT DATA Recent

------------------ Recent

FOR EACH MATERIAL TO BE PROCESSED THE MINIMUM INPUT DATA ARE THE Recent

RESONANCE PARAMETERS IN FILE 2. IF THERE ARE NO FILE 2 PARAMETERS Recent

IN A GIVEN MATERIAL THE ENTIRE MATERIAL WILL SIMPLY BE COPIED. Recent

NEITHER THE HOLLERITH SECTION (MF=1, MT=451) NOR THE BACKGROUND Recent

CROSS SECTION (SECTIONS OF MF=3) NEED BE PRESENT FOR THIS PROGRAM Recent

TO EXECUTE PROPERLY. HOWEVER, SINCE THE CONVENTIONS USED IN Recent

INTERPRETING THE RESONANCE PARAMETERS DEPENDS ON ENDF/B VERSION Recent

USERS ARE STRONGLY RECOMMENDED TO INSURE THAT MF=1, MT=451 IS Recent

PRESENT IN EACH MATERIAL TO ALLOW THE PROGRAM TO DETERMINE THE Recent

ENDF/B FORMAT VERSION. Recent

Recent

RESONANCE PARAMETERS Recent

-------------------- Recent

RESONANCE PARAMETERS MAY BE REPRESENTED USING ANY COMBINATION Recent

OF THE REPRESENTATIONS ALLOWED IN ENDF/B, Recent

(1) RESOLVED DATA Recent

(A) SINGLE LEVEL BREIT-WIGNER Recent

(B) MULTI-LEVEL BREIT-WIGNER Recent

(C) ADLER-ADLER Recent

(D) REICH-MOORE Recent

(E) HYBRID R-FUNCTION Recent

(2) UNRESOLVED DATA Recent

(A) ALL PARAMETERS ENERGY INDEPENDENT Recent

(B) FISSION PARAMETERS ENERGY DEPENDENT Recent

(C) ALL PARAMETERS ENERGY DEPENDENT Recent

Recent

THE FOLLOWING RESOLVED DATA FORMALISMS ARE NOT TREATED BY THIS Recent

VERSION OF THE CODE AND WILL ONLY BE IMPLEMENTED AFTER EVALUATIONS Recent

USING THESE FORMALISMS ARE AVAILABLE TO THE AUTHOR OF THIS CODE Recent

FOR TESTING IN ORDER TO INSURE THAT THEY CAN BE HANDLED PROPERLY Recent

(A) GENERAL R-MATRIX Recent

Recent

CALCULATED CROSS SECTIONS Recent

------------------------- Recent

THIS PROGRAM WILL USE THE RESONANCE PARAMETERS TO CALCULATE THE Recent

TOTAL, ELASTIC, CAPTURE AND POSSIBLY FISSION CROSS SECTIONS. THE Recent

COMPETITIVE WIDTH WILL BE USED IN THESE CALCULATIONS, BUT THE Recent

COMPETITIVE CROSS SECTION ITSELF WILL NOT BE CALCULATED. THE Recent

ENDF/B CONVENTION IS THAT ALTHOUGH A COMPETITIVE WIDTH MAY BE Recent

GIVEN, THE COMPETITIVE CROSS SECTION MUST BE SEPARATELY TABULATED Recent

AS A SECTION OF FILE 3 DATA. Recent

Recent

RESOLVED REGION Recent

--------------- Recent

IN THE RESOLVED REGION THE RESOLVED PARAMETERS ARE USED TO Recent

CALCULATE COLD (0 KELVIN), LINEARLY INTERPOLABLE, ENERGY DEPENDENT Recent

CROSS SECTIONS. Recent

Recent

SCATTERING RADIUS Recent

----------------- Recent

FOR SINGLE OR MULTI LEVEL BREIT-WIGNER PARAMETERS THE SCATTERING Recent

RADIUS MAY BE SPECIFIED IN EITHER ENERGY INDEPENDENT (CONSTANT) Recent

OR ENERGY DEPENDENT FORM (A TABLE OF ENERGY VS. RADIUS AND AN Recent

ASSOCIATED INTERPOLATION LAW). IN ALL OTHER CASE ONLY AN ENERGY Recent

INDEPENDENT SCATTERING RADIUS IS ALLOWED. Recent

Recent

FOR ANY ONE MATERIAL (I.E. MAT) IF ENERGY DEPENDENT SCATTERING Recent

RADII ARE GIVEN THE TOTAL NUMBER OF INTERPOLATION REGIONS AND Recent

TABULATED VALUES FOR THE ENTIRE MATERIAL CANNOT EXCEED, Recent

200 - INTERPOLATION REGIONS Recent

500 - TABULATED VALUES Recent

IF THESE LIMITS ARE EXCEEDED THE PROGRAM WILL PRINT AN ERROR Recent

MESSAGE AND TERMINATE. Recent

Recent

IF YOU REQUIRE A LARGER NUMBER OF INTERPOLATION REGION AND/OR Recent

TABULATED VALUES, Recent

(1) INTERPOLATION REGIONS - INCREASE THE DIMENSION OF NBTRHO AND Recent

INTRHO IN COMMON/TABRHO/ THROUGHOUT THE PROGRAM AND CHANGE MAXSEC Recent

IN SUBROUTINE RDAP (MAXSEC = MAXIMUM NUMBER OF INTERPOLATION Recent

REGIONS). Recent

(2) TABULATED VALUES - INCREASE THE DIMENSION OF ERHOTB, RHOTAB Recent

AND APTAB IN COMMON/TABRHO/ THROUGHOUT THE PROGRAM AND CHANGE Recent

MAXRHO IN SUBROUTINE RDAP (MAXRHO = MAXIMUM NUMBER OF TABULATED Recent

VALUES). Recent

Recent

RESOLVED REICH-MOORE AND MULTI-LEVEL BREIT-WIGNER PARAMETERS Recent

------------------------------------------------------------ Recent

CROSS SECTIONS FOR REICH-MOORE PARAMETERS ARE CALCULATED ACCORDING Recent

TO THE EQUATION (1) - (8) OF SECTION D.1.3 OF ENDF-102. IN ORDER Recent

TO CALCULATE CROSS SECTIONS FROM MULTI-LEVEL PARAMETERS IN A Recent

REASONABLE AMOUNT OF TIME THIS PROGRAM EXPRESSES THE CROSS SECTION Recent

IN TERMS OF A SINGLE SUM OVER RESONANCES (SEE, ENDF-102, SECTION Recent

D.1.2, EQUATIONS 6-7), RATHER THAN AS A DOUBLE SUM (SEE, ENDF-102 Recent

SECTION D.1.2, EQUATION 1-2). IN ORDER FOR THE ENDF-102 EQUATIONS Recent

TO BE CORRECT THE PARAMETERS MUST MEET THE FOLLOWING CONDITIONS, Recent

Recent

(1) FOR EACH L STATE ALL PHYSICALLY POSSIBLE J SEQUENCES MUST BE Recent

PRESENT. ONLY IN THIS CASE WILL THE CONTRIBUTIONS OF THE Recent

INDIVIDUAL J SEQUENCES ADD UP TO PRODUCE THE CORRECT POTENTIAL Recent

SCATTERING CONTRIBUTION FOR THE L STATE (SEE, ENDF-102, Recent

SECTION D.1.2, EQUATIONS 6-7). IF ANY J SEQUENCE IS MISSING Recent

THE PROGRAM WILL PRINT A WARNING AND ADD THE J SEQUENCE WITH Recent

NO RESONANCE PARAMETERS IN ORDER TO ALLOW THE POTENTIAL Recent

SCATTERING TO BE CALCULATED CORRECTLY (THIS IS EQUIVALENT TO Recent

ASSUMING THAT THE EVALUATOR REALIZES THAT ALL J SEQUENCES MUST Recent

BE AND ARE PRESENT AND THAT THE EVALUATION STATES THAT THERE Recent

ARE NO RESONANCES WITH CERTAIN PHYSICALLY POSSIBLE J VALUES... Recent

IN THIS CASE POTENTIAL CONTRIBUTION MUST STILL BE CONSIDERED). Recent

Recent

EXAMPLE Recent

======= Recent

AN EXAMPLE OF WHERE THIS OCCURS AND IS IMPORTANT TO CONSIDER Recent

IS U-238 IN ENDF/B-IV AND V LIBRARIES WHERE FOR L=1 THERE IS Recent

ONLY A J=1/2 SEQUENCE. NOT INCLUDING THE J=3/2 SEQUENCE LEADS Recent

TO UNDERESTIMATING THE POTENTIAL SCATTERING AND PRODUCES Recent

MINIMA IN THE ELASTIC CROSS SECTION WHICH ARE AN ORDER OF Recent

MAGNITUDE LOWER THAN THE CROSS SECTIONS OBTAINED BE INCLUDING Recent

THE J=3/2 SEQUENCE. Recent

Recent

(2) FOR A GIVEN TARGET SPIN AND L VALUE THERE MAY BE 2 POSSIBLE Recent

MEANS OF OBTAINING THE SAME J VALUE. WHEN THIS OCCURS IN Recent

ORDER TO CALCULATE THE CORRECT POTENTIAL SCATTERING CROSS Recent

SECTION IT IS IMPORTANT TO INCLUDE THE EFFECT OF BOTH Recent

POSSIBLE J SEQUENCES, EVEN THOUGH FROM THE ENDF/B DATA IT IS Recent

NOT POSSIBLE TO DETERMINE WHICH OF THE 2 POSSIBLE SEQUENCES Recent

ANY GIVEN RESONANCE BELONGS TO. IN THIS CASE THIS PROGRAM Recent

TREAT ALL RESONANCES WITH THE SAME J VALUE AS BELONGING TO Recent

THE SAME J SEQUENCE (TO ALLOW INTERFERENCE) AND WILL ADD AN Recent

ADDITIONAL J SEQUENCE WITH NO RESONANCES IN ORDER TO ALLOW Recent

THE POTENTIAL CROSS SECTION TO BE CALCULATED CORRECTLY. WHEN Recent

THIS OCCURS A WARNING MESSAGE IS PRINTED, BUT BASED ON THE Recent

ENDF/B DATA THERE IS NOTHING WRONG WITH THE DATA AND THERE IS Recent

NOTHING THAT THE USER CAN DO TO CORRECT OR IN ANY WAY MODIFY Recent

THE DATA TO ELIMINATE THE PROBLEM. Recent

Recent

EXAMPLE Recent

======= Recent

FOR A TARGET SPIN =1 AND L=1 THE 2 RANGES OF PHYSICALLY Recent

POSSIBLE J ARE 1/2, 3/2, 5/2 AND 1/2, 3/2. BY CHECKING THE Recent

ENDF/B DATA IT IS POSSIBLE TO INSURE THAT THE 3 POSSIBLE Recent

J VALUES (1/2, 3/2, 5/2) ARE PRESENT AND TO INCLUDE ALL 3 Recent

J SEQUENCES IN THE CALCULATIONS. HOWEVER, UNLESS ALL 5 Recent

POSSIBLE J SEQUENCES ARE INCLUDED THE STATISTICAL WEIGHTS Recent

OF THE J SEQUENCES WILL NOT SUM UP TO 2*L+1 AND THE Recent

POTENTIAL CROSS SECTION WILL BE UNDERESTIMATED. IN THIS Recent

EXAMPLE THE SUM OF THE 3 J SEQUENCES 1/2, 3/2, 5/2 IS 2, Recent

RATHER THAN 3 AS IT SHOULD BE FOR L=1, AND THE CONTRIBUTION Recent

OF THE L=1 RESONANCES TO THE POTENTIAL SCATTERING CROSS Recent

SECTION WILL ONLY BE 2/3 OF WHAT IT SHOULD BE, UNLESS THE Recent

OTHER 2 J SEQUENCES (WITH DUPLICATE J VALUES) ARE INCLUDED Recent

IN THE CALCULATION. Recent

Recent

(3) EACH RESONANCE MUST HAVE AN ASSIGNED, PHYSICALLY POSSIBLE Recent

J VALUE. PHYSICALLY IMPOSSIBLE OR AVERAGE J VALUES CANNOT BE Recent

UNIQUELY INTERPRETED USING THE EQUATIONS IN ENDF-102 AND Recent

THEIR USE WILL USUALLY RESULT IN PHYSICALLY UNRELIABLE CROSS Recent

SECTIONS. THIS PROGRAM WILL CHECK ALL J VALUES AND IF ANY ARE Recent

ARE FOUND TO BE PHYSICALLY IMPOSSIBLE (BASED ON TARGET SPIN Recent

AND L VALUE) AN ERROR MESSAGE WILL BE PRINTED TO INDICATE THAT Recent

THE RECONSTRUCTED CROSS SECTIONS WILL BE UNRELIABLE AND THE Recent

PROGRAM WILL CONTINUE. IN AN ATTEMPT TO CALCULATE THE CORRECT Recent

POTENTIAL SCATTERING CROSS SECTION THIS PROGRAM WILL SUBTRACT Recent

THE POTENTIAL SCATTERING CONTRIBUTION DUE TO ALL FICTICIOUS J Recent

SEQUENCES AND ADD THE CONTRIBUTION OF ALL PHYSICALLY POSSIBLE Recent

J SEQUENCES (AS DESCRIBED ABOVE). Recent

Recent

WARNING (LET THE USER BEWARE) Recent

============================= Recent

(A) IT CANNOT BE STRESSED ENOUGH THAT CROSS SECTIONS OBTAINED Recent

USING PHYSICALLY IMPOSSIBLE J VALUES FOR REICH-MOORE AND Recent

MULTI-LEVEL BREIT-WIGNER RESONANCE PARAMETERS WILL RESULT Recent

IN UNRELIABLE CROSS SECTIONS. THE DECISION TO HAVE THIS Recent

PROGRAM CONTINUE TO PROCESS WHEN THIS CONDITION IS FOUND Recent

IS BASED ON AN ATTEMPT TO ALLOW THE USER TO AT LEAST HAVE Recent

SOME RESULTS (HOWEVER BAD THEY MAY BE) IF THERE IS NO Recent

OTHER EVALUATED DATA AVAILABLE. Recent

(B) EVEN THOUGH THE REICH-MOORE AND MULTI-LEVEL EQUATIONS ARE Recent

DEFINED AS ABSOLUTE OR SQUARED CONTRIBUTIONS WHICH MUST Recent

ALL BE PHYSICALLY POSSIBLE, ATTEMPTING TO CORRECT THE Recent

POTENTIAL CROSS SECTION (AS DESCRIBED ABOVE) CAN LEAD TO Recent

NEGATIVE ELASTIC CROSS SECTIONS. THIS IS BECAUSE BASED ON Recent

THE INFORMATION AVAILABLE IN THE EVALUATION IT IS NOT Recent

NOT POSSIBLE TO CORRECTLY ACCOUNT FOR THE INTERFERENCE Recent

BETWEEN THE RESONANCE AND POTENTIAL CONTRIBUTIONS FOR EACH Recent

J SEQUENCE. Recent

Recent

UNRESOLVED RESONANCE REGION Recent

--------------------------- Recent

IN THE UNRESOLVED RESONANCE REGION THE UNRESOLVED PARAMETERS Recent

ARE USED TO CALCULATE INFINITELY DILUTE AVERAGE CROSS SECTIONS. Recent

NOTE, IT IS IMPORTANT TO UNDERSTAND THAT FROM THE DEFINITION OF Recent

THE UNRESOLVED PARAMETERS IT IS NOT POSSIBLE TO UNIQUELY CALCULATE Recent

ENERGY DEPENDENT CROSS SECTIONS. ONLY AVERAGES OR DISTRIBUTIONS Recent

MAY BE CALCULATED. Recent

Recent

UNRESOLVED INTERPOLATION Recent

------------------------ Recent

IN THE UNRESOLVED RESONANCE REGION CROSS SECTIONS AT EACH ENERGY Recent

ARE CALCULATED BY INTERPOLATING PARAMETERS. THIS IS THE CONVENTION Recent

USED IN ENDF/B-IV AND EARLIER VERSIONS OF ENDF/B. THE ENDF/B-V Recent

CONVENTION OF INTERPOLATING CROSS SECTIONS, NOT PARAMETERS, HAS Recent

BEEN ABANDONED AS IMPRACTICAL SINCE IT CAN LEAD TO THE SITUATION Recent

WHERE EXACTLY THE SAME PHYSICAL DATA CAN LEAD TO DIFFERENT RESULTS Recent

DEPENDING ON WHICH OF THE THREE ENDF/B UNRESOLVED PARAMTER FORMATS Recent

IS USED. FOR EXAMPLE, GIVEN A SET OF ENERGY INDEPENDENT UNRESOLVED Recent

PARAMETERS IT IS POSSIBLE TO CODE THESE PARAMETERS IN EACH OF THE Recent

THREE ENDF/B UNRESOLVED PARAMETER FORMATS. SINCE PHYSICALLY WE Recent

ONLY HAVE ONE SET OF PARAMETERS WE WOULD EXPECT THE RESULTS TO BE Recent

INDEPENDENT OF HOW THEY ARE REPRESENTED IN ENDF/B. UNFORTUNATELY Recent

USING THE ENDF/B-V CONVENTION TO INTERPOLATE CROSS SECTIONS CAN Recent

LEAD TO THREE COMPLETELY DIFFERENT RESULTS. IN CONTRAST USING THE Recent

ENDF/B-IV AND EARLIER CONVENTION OF INTERPOLATING PARAMETERS LEADS Recent

TO COMPLETELY CONSISTENT RESULTS. Recent

Recent

INTERNAL REPRESENTATION OF UNRESOLVED PARAMETERS Recent

------------------------------------------------ Recent

ANY OF THE THREE POSSIBLE REPRESENTATIONS OF UNRESOLVED PARAMETERS Recent

CAN BE UNIQUELY REPRESENTED IN THE ALL PARAMETERS ENERGY DEPENDENT Recent

REPRESENTATIONS WITH THE APPROPRIATE (ENDF/B VERSION DEPENDENT) Recent

INTERPOLATION LAW. THIS IS DONE BY THE PROGRAM WHILE READING THE Recent

UNRESOLVED PARAMETERS AND ALL SUBSEQUENT CALCULATIONS NEED ONLY Recent

CONSIDER THE ALL PARAMETERS ENERGY DEPENDENT REPRESENTATION. Recent

Recent

RESONANCE RECONSTRUCTION STARTING ENERGY GRID Recent

--------------------------------------------- Recent

AS IN ANY ITERATIVE METHOD THE WAY TO SPEED CONVERGENCE IS TO TRY Recent

TO START CLOSE TO THE ANSWER. THIS PROGRAM ATTEMPTS TO DO THIS BY Recent

STARTING FROM AN ENERGY GRID WHICH IS A GOOD APPROXIMATION TO A Recent

SIMPLE BREIT-WIGNER LINE SHAPE, Recent

Recent

SIGMA(X)=1.0/(1.0+X*X) Recent

Recent

WHERE X IS THE DISTANCE FROM THE PEAK IN HALF-WIDTHS Recent

Recent

SUBROUTINE SUBINT HAS A BUILT-IN TABLE OF NODES WHICH ARE THE Recent

HALF-WIDTH MULTIPLES TO APPROXIMATE THE SIMPLE BREIT-LINE SHAPE Recent

TO WITHIN 1 PER-CENT OVER THE ENTIRE INTERVAL 0 TO 500 HALF-WIDTHS Recent

Recent

BETWEEN ANY TWO RESOLVED RESONANCES THE STARTING GRID IS BASED ON Recent

THE HALF-WIDTHS OF THE TWO RESONANCES. FROM THE LOWER ENERGY Recent

RESONANCE UP TO THE MID-POINT BETWEEN THE RESONANCES (MID-POINT Recent

IS DEFINED HERE AS AN EQUAL NUMBER OF HALF-WIDTHS FROM EACH Recent

RESONANCE) THE HALF-WIDTH OF THE LOWER ENERGY RESONANCE IS USED. Recent

FROM THE MID-POINT UP TO THE HIGHER ENERGY RESONANCE THE HALF- Recent

WIDTH OF THE UPPER ENERGY RESONANCE IS USED. Recent

Recent

WITH THIS ALOGORITHM CLOSELY SPACED RESONANCES WILL HAVE ONLY Recent

A FEW STARTING NODES PER RESONANCE (E.G. U-235). WIDELY SPACED Recent

RESONANCES WILL HAVE MORE NODES PER RESONANCE (E.G. U-238). FOR Recent

A MIX OF S, P, D ETC. RESONANCES THIS ALOGORITHM GUARANTEES AN Recent

ADEQUTE DESCRIPTION OF THE PROFILE OF EVEN EXTREMELY NARROW Recent

RESONANCES (WHICH MAY IMMEDIATELY CONVERGENCE TO THE ACCURACY Recent

REQUESTED, THUS MINIMIZING ITERATION). Recent

Recent

BACKGROUND CROSS SECTIONS Recent

------------------------- Recent

THE PROGRAM WILL SEARCH FOR BACKGROUND CROSS SECTIONS FOR TOTAL Recent

(MT=1), ELASTIC (MT=2), FISSION (MT=18), FIRST CHANCE FISSION Recent

(MT=19) AND CAPTURE (MT=102). Recent

Recent

(1) THE BACKGROUND CROSS SECTIONS (FILE 3) CAN BE PRESENT OR NOT Recent

PRESENT FOR EACH REACTION. Recent

(2) IF FOR A GIVEN REACTION THE BACKGROUND CROSS SECTION IS Recent

PRESENT, IT WILL BE ADDED TO THE RESONANCE CONTRIBUTION AND Recent

THE RESULT WILL BE OUTPUT. Recent

(3) IF FOR A GIVEN REACTION THE BACKGROUND IS NOT PRESENT THE Recent

PROGRAM WILL, Recent

(A) IF THE INPUT TO THE PROGRAM SPECIFIES NO OUTPUT FOR Recent

REACTIONS WITH NO BACKGROUND THERE WILL BE NO OUTPUT. Recent

(B) IF THE INPUT TO THE PROGRAM SPECIFIES OUTPUT FOR REACTIONS Recent

WITH NO BACKGROUND, Recent

(I) THE RESONANCE CONTRIBUTION TO TOTAL, ELASTIC OR Recent

CAPTURE WILL BE OUTPUT. Recent

(II) IF ALL FISSION RESONANCE PARAMETERS ARE ZERO THE Recent

FISSION CROSS SECTION (MT=18) WILL NOT BE OUTPUT. Recent

OTHERWISE THE RESONANCE CONTRIBUTION OF THE FISSION Recent

(MT=18) WILL BE OUTPUT. Recent

(III) THERE WILL BE NO OUTPUT FOR FIRST CHANCE FISSION Recent

(MT=19). Recent

Recent

COMBINING RESONANCES AND BACKGROUND CROSS SECTIONS Recent

-------------------------------------------------- Recent

IN ORDER TO BE COMBINED WITH THE RESONANCE CONTRIBUTION THE Recent

BACKGROUND CROSS SECTIONS MUST BE GIVEN AT 0 KELVIN TEMPERATURE Recent

AND MUST BE LINEARLY INTERPOLABLE. IF THESE CONDITIONS ARE MET Recent

THE RESONANCE AND BACKGROUND CONTRIBUTIONS WILL BE ADDED TOGETHER Recent

AND OUTPUT. IF THESE CONDITIONS ARE NOT MET THE BACKGROUND CROSS Recent

SECTION WILL BE IGNORED AND ONLY THE RESONANCE CONTRIBUTION WILL Recent

BE OUTPUT. IF THE BACKGROUND HAS NOT BEEN ADDED TO THE RESONANCE Recent

CONTRIBUTION AFTER THIS PROGRAM FINISHES THE USER CAN MAKE THE Recent

RESONANCE AND BACKGROUND CONTRIBUTIONS COMPATIBLE BY, Recent

Recent

(1) IF THE BACKGROUND IS NOT LINEARLY INTERPOABLE, LINEARIZE THE Recent

BACKGROUND (E.G., USE PROGRAM LINEAR). Recent

(2) IF THE BACKGROUND IS NOT GIVEN AT 0 KELVIN, DOPPLER BROADEN Recent

THE RESONANCE (NOT BACKGROUND) CONTRIBUTION TO THE SAME Recent

TEMPERATURE AS THE BACKGROUND (E.G., USE PROGRAM SIGMA1). Recent

Recent

ONCE THE RESONANCE AND BACKGROUND CONTRIBUTIONS HAVE BEEN MADE Recent

COMPATIBLE THEY CAN BE ADDED TOGETHER (E.G., USE PROGRAM MIXER). Recent

Recent

THE RECONSTRUCTION OF THE RESONANCE CONTRIBUTION TO THE CROSS Recent

SECTION CAN BE QUITE EXPENSIVE (IN TERMS OF COMPUTER TIME). SINCE Recent

THE RECONSTRUCTION IS PERFORMED BEFORE THE BACKGROUND CROSS Recent

SECTIONS ARE READ, THE ABOVE CONVENTIONS HAVE BEEN ADOPTED IN Recent

ORDER TO AVOID LOSE OF COMPUTER TIME INVOLVED IN RECONSTRUCTING Recent

THE RESONANCE CONTRIBUTION. Recent

Recent

COMMON ENERGY GRID Recent

------------------ Recent

THIS PROGRAM WILL RECONSTRUCT THE RESONANCE CONTRIBUTION TO THE Recent

TOTAL, ELASTIC, FISSION AND CAPTURE CROSS SECTIONS ALL ON THE Recent

SAME ENERGY GRID. EACH REACTION WILL THEN BE COMBINED WITH ITS Recent

BACKGROUND CROSS SECTION (IF ANY) AND OUTPUT WITHOUT ANY FURTHER Recent

THINNING. IF THERE ARE NO BACKGROUND CROSS SECTIONS, OR IF THE Recent

BACKGROUND CROSS SECTION FOR ALL FOUR REACTIONS ARE GIVEN ON A Recent

COMMON ENERGY GRID, THE OUTPUT FROM THIS PROGRAM WILL BE ON A Recent

COMMON ENERGY GRID FOR ALL FOUR REACTIONS. Recent

Recent

THERMAL ENERGY Recent

-------------- Recent

IF THE RESONANCE REGION SPANS THERMAL ENERGY (0.0253 EV) THIS Recent

POINT IS ALWAYS INCLUDED IN THE COMMON ENERGY GRID USED FOR ALL Recent

REACTIONS AND WILL ALWAYS APPEAR IN THE OUTPUT DATA. Recent

Recent

SECTION SIZE Recent

------------ Recent

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Recent

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Recent

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Recent

Recent

SELECTION OF DATA Recent

----------------- Recent

THE PROGRAM SELECTS MATERIALS TO BE PROCESSED BASED EITHER ON Recent

MAT (ENDF/B MAT NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR Recent

ZA RANGES TO BE SPECIFIED. THE PROGRAM WILL ASSUME THAT THE Recent

ENDF/B TAPE IS IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS Recent

USED TO SELECT MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA Recent

IS FOUND THAT IS ABOVE THE RANGE OF ALL REQUESTS. Recent

Recent

ALLOWABLE ERROR Recent

--------------- Recent

THE RECONSTRUCTION OF LINEARLY INTERPOLABLE CROSS SECTIONS FROM Recent

RESONANCE PARAMETERS CANNOT BE PERFORMED EXACTLY. HOWEVER IT CAN Recent

BE PERFORMED TO VIRTUALLY ANY REQUIRED ACCURACY AND MOST Recent

IMPORTANTLY CAN BE PERFORMED TO A TOLERANCE THAT IS SMALL COMPARED Recent

TO THE UNCERTAINTY IN THE CROSS SECTIONS THEMSELVES. AS SUCH THE Recent

CONVERSION OF CROSS SECTIONS TO LINEARLY INTERPOLABLE FORM CAN BE Recent

PERFORMED WITH ESSENTIALLY NO LOSS OF INFORMATION. Recent

Recent

THE ALLOWABLE ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Recent

DEPENDENT. THE ALLOWABLE ERROR IS DESCRIBED BY A TABULATED Recent

FUNCTION OF UP TO 20 (ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Recent

BETWEEN TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Recent

ERROR WILL BE CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE. Recent

WITH THIS ENERGY DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR Recent

ANY GIVEN APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE Recent

OF INTEREST AND A LESS STRINGENT ERROR IN OTHER ENERGY RANGES, Recent

E.G., 0.1 PER-CENT FROM 0 UP TO THE LOW EV RANGE AND A LESS Recent

STRINGENT TOLERANCE AT HIGHER ENERGIES. Recent

Recent

DEFAULT ALLOWABLE ERROR Recent

----------------------- Recent

IN ORDER TO INSURE CONVERENCE OF THE RESONANCE RECONSTRUCTION THE Recent

ALLOWABLE ERROR MUST BE POSITIVE. IF THE USER INPUTS AN ERROR FOR Recent

RESONANCE RECONSTRUCTION THAT IS NOT POSITIVE IT WILL BE SET TO Recent

THE DEFAULT VALUE (CURRENTLY 0.1 PER-CENT) AND INDICATED AS SUCH Recent

IN THE OUTPUT LISTING. Recent

Recent

INTERVAL HALVING ALGORITHM Recent

------------------------- Recent

THIS PROGRAM WILL START BY CALCULATING THE CROSS SECTIONS AT THE Recent

ENERGIES CORRESPONDING TO THE PEAK OF EACH RESONANCE, AS WELL AS Recent

A FIXED NUMBER OF HALF-WIDTHS ON EACH SIDE OF EACH RESONANCE. Recent

STARTING FROM THIS BASIC GRID OF POINTS THE PROGRAM WILL CONTINUE Recent

TO HALF EACH INTERVAL UNTIL THE CROSS SECTIONS FOR ALL REACTIONS Recent

AT THE CENTER OF THE INTERVAL CAN BE DEFINED BY LINEAR Recent

INTERPOLATION FROM THE ENDS OF THE INTERVAL TO WITHIN THE USER Recent

SPECIFIED ACCURACY CRITERIA. Recent

Recent

DISTANT RESONANCE TREATMENT Recent

--------------------------- Recent

THE OPTION TO TREAT DISTANT RESONANCES, WHICH WAS AVAILABLE IN Recent

EARLIER VERSIONS OF THIS PROGRAM, IS NO LONGER AVAILABLE, BECAUSE Recent

IT WAS FOUND TO PRODUCE UNRELIABLE RESULTS. IN THIS VERSION OF Recent

THE PROGRAM ALL RESONANCES ARE TREATED EXACTLY. Recent

Recent

PROGRAM OPERATION Recent

================================================================== Recent

EDIT MODE Recent

--------- Recent

IT IS SUGGESTED THAT BEFORE RUNNING THIS PROGRAM TO RECONSTRUCT Recent

CROSS SECTIONS FROM RESONANCE PARAMETERS (WHICH CAN BE QUITE Recent

EXPENSIVE) THE USER FIRST RUN THE PROGRAM IN THE EDIT MODE (SEE, Recent

DESCRIPTION OF INPUT PARAMETERS BELOW). IN THE EDIT MODE THE Recent

PROGRAM WILL READ, LIST AND EXTENSIVELY CHECK THE CONSISTENCY OF Recent

ALL RESONANCE PARAMETERS AND ENDF/B DEFINED RESONANCE FLAGS. THIS Recent

IS A VERY INEXPENSIVE MEANS OF CHECKING ALL DATA BEFORE INVESTING Recent

A LARGE AMOUNT OF MONEY IN RECONSTRUCTING CROSS SECTIONS. ANY AND Recent

ALL DIGNOSTICS RECEIVED FROM THE EDIT WILL SUGGEST HOW TO CORRECT Recent

THE EVALUATED DATA TO MAKE IT CONSISTENT BEFORE RECONSTRUCTING Recent

CROSS SECTIONS. IN ORDER TO OBTAIN MEANINGFUL RESULTS FROM THE Recent

RECONSTRUCTION ALL SUGGESTED CHANGES TO THE EVALUATION SHOULD BE Recent

PERFORMED BEFORE TRYING RECONSTRUCTION (OTHERWISE THE RESULT OF Recent

RECONSTRUCTION WILL NOT BE RELIABLE). Recent

Recent

RECONSTRUCTION MODE Recent

------------------- Recent

FOR EACH REQUESTED MATERIAL Recent

--------------------------- Recent

IF SECTION MF=1, MT=451 IS PRESENT COMMENTS WILL BE ADD TO Recent

DOCUMENT THAT THE MATERIAL HAS BEEN PROCESSED. MF=1, MT=451 WILL Recent

ALSO BE USED TO DETERMINE THE VERSION OF THE ENDF/B FORMAT WHICH Recent

WILL ALLOW THE PROGRAM TO USE THE APPROPRIATE CONVENTIONS. Recent

Recent

ALL OF THE FILE 2 RESONANCE PARAMETERS ARE FIRST READ AND THE Recent

LINEARLY INTERPOLABLE CONTRIBUTION OF THE RESONANCE PARAMETERS Recent

TO THE TOTAL, ELASTIC, CAPTURE AND FISSION CROSS SECTIONS IS Recent

CALCULATED SIMULTANEOUSLY USING A COMMON ENERGY GRID FOR ALL Recent

FOUR REACTIONS. Recent

Recent

AFTER THE RESONANCE CONTRIBUTION HAS BEEN RECONSTRUCTED EACH OF Recent

THE FIVE REACTIONS (MT=1, 2, 18, 19, 102) IS CONSIDERED SEPARATELY Recent

FOR COMBINATION WILL THE BACKGROUND CROSS SECTION, IF ANY, AS Recent

DESCRIBED ABOVE. Recent

Recent

OUTPUT WILL INCLUDE THE ENTIRE EVALUATION, INCLUDING RESONANCES Recent

PARAMETERS WITH LRU MODIFIED (AS DESCRIBED ABOVE) TO INDICATE Recent

THAT THE RESONANCE CONTRIBUTION HAS ALREADY BEEN ADDED TO THE Recent

FILE 3 CROSS SECTIONS. Recent

Recent

THE CYCLE OF RECONSTRUCTING THE RESONANCE CONTRIBUTION AND ADDING Recent

THE BACKGROUND WILL BE REPEATED FOR EACH MATERIAL REQUESTED. Recent

Recent

PROCESS ONLY A PORTION OF RESONANCE REGION Recent

================================================================== Recent

MODERN EVALUATIONS MAY BE EXTREMELY LARGE AND IT MAY NOT BE Recent

POSSIBLE TO PROCESS AN ENTIRE EVALUATION (I.E., ADD THE RESONANCE Recent

CONTRIBUTION) DURING A SINGLE COMPUTER RUN. Recent

Recent

ALSO IN THE CASE WHERE YOU ARE ONLY INTERESTED IN THE CROSS Recent

SECTIONS OVER A SMALL ENERGY RANGE, YOU MAY NOT WANT TO PROCESS Recent

AN ENTIRE EVALUATION, E.G., IF YOU ONLY WANT TO KNOW WHAT THE Recent

CROSS SECTIONS ARE NEAR THERMAL ENERGY, 0.0253 EV. Recent

Recent

IN ORDER TO ALLOW AN EVALUATION TO BE PROCESSED USING A NUMBER OF Recent

SHORTER COMPUTER RUNS AN OPTION HAS BEEN ADDED TO THIS PROGRAM TO Recent

ALLOW THE USER TO SPECIFY THE ENERGY RANGE TO BE PROCESSED. Recent

Recent

USING THIS OPTION YOU MAY START AT THE LOWEST ENERGY (ZERO UP TO Recent

SOME ENERGY) AND USE THE RESULTS OF THIS RUN AS INPUT TO THE Recent

NEXT RUN, WHERE YOU CAN SPECIFY THE NEXT ENERGY RANGE. THIS Recent

CYCLE CAN BE REPEATED UNTIL YOU HAVE PROCESSED THE ENTIRE Recent

EVALUATION. Recent

Recent

WARNING - THIS OPTION SHOULD BE USED WITH EXTREME CARE - THIS Recent

OPTION HAS BEEN RELUCTANTLY ADDED - RELUCTANTLY BECAUSE IT CAN Recent

BE EXTREMELY DANGEROUS TO USE THIS OPTION UNLESS YOU CAREFULLY Recent

CHECKED WHAT YOU ARE DOING. Recent

Recent

THE OPTION SHOULD ONLY BE USED AS FOLLOWS, Recent

1) YOU MUST PROCESS USING ENERGY RANGES STARTING AT LOW ENERGY Recent

AND WORKING YOUR WAY TOWARD HIGH ENERGY, E.G., Recent

0.0 TO 3.0+3 Recent

3.0+3 TO 10.0+3 Recent

10.0+3 TO 80.0+3, ETC. Recent

2) FOR THE LAST ENERGY RANGE THE LOWER ENERGY LIMIT MUST BE Recent

NON-ZERO (WHERE TO START) AND THE UPPER ENERGY LIMIT MUST Recent

BE ZERO (NO LIMIT) Recent

80.0+3 TO 0.0 Recent

Recent

IF YOU ARE ONLY INTERESTED IN THE CROSS SECTION OVER A NARROW Recent

ENERGY INTERVAL AND DO NOT INTENT TO MAKE ANY OTHER USE OF THE Recent

RESULTS, YOU CAN IGNORE THESE WARNINGS AND MERELY SPECIFY ANY Recent

ENERGY INTERVAL OVER WHICH YOU WISH CALCULATIONS TO BE Recent

PERFORMED. Recent

Recent

NORMALLY WHEN THIS PROGRAM PROCESSES AN EVALUATION IT WILL SET Recent

FLAGS IN THE EVALUATION TO PREVENT THE SAME RESONANCE Recent

CONTRIBUTION FROM BEING ADDED TO THE CROSS SECTION MORE THAN Recent

ONCE, SHOULD YOU USE THE OUTPUT FROM THIS PROGRAM AS INPUT TO Recent

THE PROGRAM. Recent

Recent

WHEN PROCESSING ONLY PORTIONS OF THE RESONANCE REGION THIS Recent

PROGRAM CANNOT SET THESE FLAGS TO PROTECT AGAINST ADDING THE Recent

RESONANCE CONTRIBUTION MORE THAN ONCE - WHICH MAKES USE OF Recent

THIS OPTION EXTREMELY DANGEROUS. Recent

Recent

ONLY YOU CAN CHECK TO MAKE SURE THAT YOU HAVE CORRECTLY Recent

INCLUDED EACH ENERGY RANGE ONLY ONCE - SEE THE COMMENT LINES Recent

AT THE END OF SECTION, MF=1, MT=451, FOR A COMPLETE RECORD Recent

OF EACH RUN USING THIS PROGRAM. THIS SECTION WILL CONTAIN Recent

LINES OF THE FORM Recent

Recent

***************** PROGRAM RECENT (VERSION 2004-1) ************* Recent

ONLY PROCESS 0.00000+ 0 TO 3.00000+ 3 EV Recent

***************** PROGRAM RECENT (VERSION 2004-1) ************* Recent

ONLY PROCESS 3.00000+ 3 TO 1.00000+ 4 EV Recent

***************** PROGRAM RECENT (VERSION 2004-1) ************* Recent

ONLY PROCESS 1.00000+ 4 TO 8.00000+ 4 EV Recent

***************** PROGRAM RECENT (VERSION 2004-1) ************* Recent

ONLY PROCESS 8.00000+ 4 TO 2.00000+ 7 EV Recent

Recent

YOU SHOULD CHECK TO INSURE THAT THERE ARE NO OVERLAPPING ENERGY Recent

RANGES OR MISSING ENERGY RANGES. Recent

Recent

WHEN YOU INDICATE BY INPUT THAT YOU ARE ABOUT TO PROCESS THE Recent

LAST ENERGY RANGE (SEE ABOVE, LOWER ENERGY LIMIT = NON-ZERO, Recent

UPPER ENERGY LIMIT = ZERO), THIS PROGRAM WILL ASSUME THAT Recent

YOU HAVE NOW COMPLETED ALL PROCESSING - AND ONLY THEN WILL Recent

IT SET FLAGS IN THE EVALUATION TO PREVENT THE RESONANCE Recent

CONTRIBUTION FROM BEING ADDED MORE THAN ONCE. FOR THIS REASON Recent

YOU CANNOT PROCESS STARTING WITH ENERGY INTERVALS AT HIGH Recent

ENERGY AND WORKING TOWARD LOW ENERGY - YOU MUST START AT LOW Recent

ENERGY AND WORK TOWARD HIGH ENERGY. Recent

Recent

I/O FILES Recent

================================================================== Recent

INPUT FILES Recent

----------- Recent

UNIT DESCRIPTION Recent

---- ----------- Recent

2 INPUT LINE (BCD - 80 CHARACTERS/RECORD) Recent

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Recent

Recent

OUTPUT FILES Recent

------------ Recent

UNIT DESCRIPTION Recent

---- ----------- Recent

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Recent

11 FINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Recent

Recent

SCRATCH FILES Recent

------------- Recent

UNIT DESCRIPTION Recent

---- ----------- Recent

12 SCRATCH FILE FOR DATA RECONSTRUCTED FROM RESONANCE Recent

PARAMETERS (BINARY - 100200 WORDS/RECORD) Recent

14 SCRATCH FILE FOR COMBINED FILE 2 AND 3 DATA Recent

(BINARY - 40080 WORDS/RECORD) Recent

Recent

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILEIO) Recent

================================================================== Recent

UNIT FILE NAME Recent

---- ---------- Recent

2 RECENT.INP Recent

3 RECENT.LST Recent

10 ENDFB.IN Recent

11 ENDFB.OUT Recent

12 (SCRATCH) Recent

14 (SCRATCH) Recent

Recent

INPUT CARDS Recent

================================================================== Recent

LINE COLS. FORMAT DESCRIPTION Recent

---- ----- ------ ----------- Recent

1 1-11 I11 RETRIEVAL CRITERIA (0=MAT, 1=ZA) Recent

THIS OPTION DEFINED WHETHER COLUMNS 1-22 OF Recent

SUBSEQUENT INPUT CARDS SHOULD BE INTERPRETED Recent

TO BE MAT OR ZA RANGES. Recent

12-22 E11.4 FILE 2 MINIMUM ABSOLUTE CROSS SECTION Recent

(IF 1.0E-10 OR LESS IS INPUT THE PROGRAM Recent

WILL USE 1.0E-10) Recent

23-33 I11 TREATMENT OF REACTIONS FOR WHICH BACKGROUND Recent

CROSS SECTION IS NOT GIVEN. Recent

= 0 - IGNOR (I.E. NO OUTPUT) Recent

= 1 - OUTPUT RESONANCE CONTRIBUTION. Recent

THIS OPTION IS USEFUL WITH PARTIAL EVALUATION Recent

(E.G. ENDF/B-V DOSIMETRY LIBRARY) WHERE ONLY Recent

ONE OR MORE OF THE REACTIONS ARE OF ACTUAL Recent

INTEREST. Recent

WARNING...THE USE OF THIS FIELD HAS BEEN Recent

CHANGED. THIS FIELD WAS PREVIOUSLY USED TO Recent

DEFINE THE PRECISION OF THE CALCULATION AND Recent

OUTPUT. THE FORMER DEFINITION OF THIS FIELD Recent

WAS... Recent

MINIMUM ENERGY SPACING FLAG Recent

= 0 - 6 DIGIT MINIMUM ENERGY SPACING. Recent

STANDARD 6 DIGIT E11.4 OUTPUT. Recent

= 1 - 9 DIGIT MINIMUM ENERGY SPACING. Recent

STANDARD 6 DIGIT E11.4 OUTPUT. Recent

= 2 - 9 DIGIT MINIMUM ENERGY SPACING. Recent

VARIABLE 9 DIGIT F FORMAT OUTPUT. Recent

FROM EXPERIENCE IT HAS BEEN FOUND THAT Recent

FAILURE TO SET THIS OPTION TO 2 CAN RESULT Recent

IN LARGE ERRORS IN THE FINAL DATA. THEREFORE Recent

INTERNALLY THIS OPTION IS SET TO 2. Recent

34-44 I11 OPERATING MODE Recent

= 0 - CACULATE. MINIMUM OUTPUT LISTING Recent

= 1 - CACULATE. LIST ALL RESONANCE PARAMETERS Recent

= 2 - EDIT MODE. NO CALCULATION. LIST ALL Recent

RESONANCE PARAMETERS. Recent

NOTE, THE EDIT MODE (=2) IS THE SUGGESTED Recent

MODE TO FIRST TEST THE CONSISTENCY OF THE Recent

EVALUATED DATA, BEFORE RECONSTRUCTING CROSS Recent

SECTIONS (SEE, COMMENTS ABOVE). Recent

45-55 I11 THIS OPTION IS NO LONGER USED. THE PREVIOUS Recent

DEFINITION OF THIS OPTION WAS---DISTANT Recent

RESONANCE TREATMENT. Recent

= 0 - EXACT Recent

= 1 - LINEAR RATIO OVER SUBINTERVAL Recent

= 2 - LINEAR RATIO OVER INTERVAL Recent

ALL RESONANCES ARE TREATED EXACTLY IN THIS Recent

VERSION OF THE CODE. Recent

56-66 I11 MONITOR MODE SELECTOR Recent

= 0 - NORMAL OPERATION Recent

= 1 - MONITOR PROGRESS OF RECONSTRUCTION OF Recent

FILE 2 DATA AND COMBINING FILE 2 AND Recent

FILE 3 DATA. EACH TIME A PAGE OF DATA Recent

POINTS IS WRITTEN TO A SCRATCH FILE Recent

PRINT OUT THE TOTAL NUMBER OF POINTS Recent

ON SCRATCH AND THE LOWER AND UPPER Recent

ENERGY LIMITS OF THE PAGE (THIS OPTION Recent

MAY BE USED IN ORDER TO MONITOR THE Recent

EXECUTION SPEED OF LONG RUNNING JOBS). Recent

2 1-60 A60 ENDF/B INPUT DATA FILENAME Recent

(STANDARD OPTION = ENDFB.IN) Recent

3 1-60 A60 ENDF/B OUTPUT DATA FILENAME Recent

(STANDARD OPTION = ENDFB.OUT) Recent

4-N 1-11 I11 MINIMUM MAT OR ZA (SEE COLS. 1-11, LINE 1) Recent

12-22 I11 MAXIMUM MAT OR ZA (SEE COLS. 1-11, LINE 1) Recent

UP TO 100 MAT OR ZA RANGES MAY BE SPECIFIED, Recent

ONE RANGE PER LINE. THE LIST IS TERMINATED Recent

BY A BLANK LINE. IF THE THE UPPER LIMIT OF Recent

ANY REQUEST IS LESS THAN THE LOWER LIMIT THE Recent

UPPER LIMIT WILL BE SET EQUAL TO THE LOWER Recent

LIMIT. IF THE FIRST REQUEST LINE IS BLANK IT Recent

WILL TERMINATE THE REQUEST LIST AND CAUSE ALL Recent

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT). Recent

23-33 E11.4 LOWER ENERGY LIMIT FOR PROCESSING. Recent

34-44 E11.4 UPPER ENERGY LIMIT FOR PROCESSING. Recent

*THE LOWER AND UPPER ENERGY LIMITS MUST BE Recent

ZERO, OR BLANK, UNLESS YOU WISH TO ONLY Recent

PROCESS A PORTION OF RESONANCE REGIONS. Recent

*THESE ENERGY LIMITS ARE ONLY READ FROM THE Recent

FIRST MAT/ZA REQUEST LINE Recent

*IF BOTH ARE ZERO (OR BLANK) THE ENTIRE Recent

RESONANCE REGION FOR EACH MATERIAL WILL BE Recent

PROCESSED Recent

*IF LIMITS ARE INPUT ONLY THAT PORTION OF THE Recent

RESONANCE REGION FOR EACH MATERIAL WHICH Recent

LIES BETWEEN THESE LIMITS WILL BE PROCESSED Recent

*SEE INSTRUCTIONS ABOVE BEFORE USING THIS Recent

OPTION. Recent

VARY 1-11 E11.4 ENERGY FOR FILE 2 ERROR LAW ( SEE ) Recent

12-22 E11.4 ERROR FOR FILE 2 ERROR LAW (COMMENTS) Recent

( BELOW ) Recent

Recent

NOTE, THIS VERSION OF THE PROGRAM DOES NOT THIN THE COMBINED FILE Recent

FILE 2 + 3 DATA. AS SUCH THE ERROR LAW FOR COMBINING FILE 2 + 3 Recent

WHICH WAS REQUIRED IN EARLIER VERSIONS OF THIS CODE ARE NO LONGER Recent

REQUIRED. Recent

Recent

THE FILE 2 ERROR LAW MAY BE ENERGY INDEPENDENT (DEFINED BY A Recent

SINGLE ERROR) OR ENERGY DEPENDENT (DEFINED BY UP TO 20 ENERGY, Recent

ERROR PAIRS). FOR THE ENERGY DEPENDENT CASE LINEAR INTERPOLATION Recent

WILL BE USED TO DEFINE THE ERROR AT ENERGIES BETWEEN THOSE AT Recent

WHICH THE ERROR IS TABULATED. THE ERROR LAW IS TERMINATED BY A Recent

BLANK LINE. IF ONLY ONE ENERGY, ERROR PAIR IS GIVEN THE LAW WILL Recent

BE CONSIDERED TO BE ENERGY INDEPENDENT. IF MORE THAN ONE PAIR Recent

IS GIVEN IT BE CONSIDERED TO BE ENERGY DEPENDENT (NOTE, THAT Recent

FOR A CONSTANT ERROR THE ENERGY INDEPENDENT FORM WILL RUN FASTER. Recent

HOWEVER, FOR SPECIFIC APPLICATIONS AN ENERGY DEPENDENT ERROR MAY Recent

BY USED TO MAKE THE PROGRAM RUN CONSIDERABLE FASTER). Recent

Recent

ALL ENERGIES MUST BE IN ASCENDING ENERGY ORDER. FOR CONVERGENCE Recent

OF THE FILE 2 RECONSTRUCTION ALGORITHM ALL THE ERRORS MUST BE Recent

POSITIVE. IF ERROR IS NOT POSITIVE IT WILL BE SET EQUAL TO THE Recent

STANDARD OPTION (CURRENTLY 0.001, CORRRESPONDING TO 0.1 PER-CENT). Recent

IF THE FIRST LINE OF THE ERROR LAW IS BLANK IT WILL TERMINATE THE Recent

ERROR LAW AND THE ERROR WILL BE TREATED AS ENERGY INDEPENDENT, Recent

EQUAL TO THE STANDARD OPTION (CURRENTLY, 0.1 PER-CENT). SEE, Recent

EXAMPLE INPUT 4. Recent

Recent

EXAMPLE INPUT NO. 1 Recent

------------------- Recent

CONSIDER ALL URANIUM ISOTOPES AND TH-232. CONSIDER CROSS SECTIONS Recent

WHICH ARE LARGER THAN 1.0E-8 BARNS IN ABSOLUTE VALUE. ONLY OUTPUT Recent

REACTIONS FOR WHICH A BACKGROUND IS GIVEN. LIST ALL PARAMETERS AND Recent

CALCULATE CROSS SECTIONS. MONITOR THE EXECUTION PROGRESS OF THE Recent

PROGRAM. BETWEEN 0 AND 100 EV USE 0.1 PER-CENT ACCURACY. BETWEEN Recent

100 EV AND 1 KEV VARY THE ACCURACY FROM 0.1 TO 1 PER-CENT. ABOVE Recent

1 KEV USE 1 PER-CENT ACCURACY. Recent

Recent

EXPLICITLY SPECIFY THE STANDARD FILENAMES. Recent

Recent

THE FOLLOWING 11 INPUT CARDS ARE REQUIRED. Recent

Recent

1 1.00000-08 0 1 0 1 Recent

ENDFB.IN Recent

ENDFB.OUT Recent

92000 92999 Recent

90232 (UPPER LIMIT AUTOMATICALLY SET TO 90232) Recent

(END REQUEST LIST) Recent

0.00000+ 0 1.00000-03 Recent

1.00000+02 1.00000-03 Recent

1.00000+03 1.00000-02 Recent

1.00000+09 1.00000-02 Recent

(END FILE 2 ERROR LAW) Recent

Recent

EXAMPLE INPUT NO. 2 Recent

------------------- Recent

CONSIDER ALL URANIUM ISOTOPES AND TH-232. CONSIDER CROSS SECTIONS Recent

WHICH ARE LARGER THAN 1.0E-8 BARNS IN ABSOLUTE VALUE. ONLY OUTPUT Recent

REACTIONS FOR WHICH A BACKGROUND IS GIVEN. CROSS SECTIONS WILL BE Recent

CALCULATED, BUT PARAMETERS WILL NOT BE LISTED. THE PROGRESS OF THE Recent

PROGRAM WILL NOT BE MONITORED. USE 0.1 PER-CENT ACCURACY FOR ALL Recent

ENERGIES. SINCE 0.1 PER-CENT IS THE STANDARD OPTION FOR THE ERROR Recent

LAW THE FIRST ERROR LAW LINE MAY BE LEFT BLANK. Recent

Recent

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Recent

THEN USE THE STANDARD FILENAMES. Recent

Recent

THE FOLLOWING 7 INPUT CARDS ARE REQUIRED. Recent

Recent

1 1.00000-08 0 0 0 0 Recent

Recent

Recent

92000 92999 Recent

90232 (UPPER LIMIT AUTOMATICALLY SET TO 90232) Recent

(END REQUEST LIST) Recent

(USE STANDARD OPTION FOR ERROR LAW) Recent

Recent

EXAMPLE INPUT NO. 3 Recent

------------------- Recent

THE SAME AS EXAMPLE INPUT NO. 2, ONLY IN THIS CASE ONLY CALCULATE Recent

CROSS SECTIONS OVER THE ENERGY RANGE 0.01 TO 0.1 EV - ACROSS THE Recent

THERMAL ENERGY RANGE. NOTE, THE ONLY DIFFERENCE BETWEEN THE INPUT Recent

PARAMETERS IN THIS CASE AND IN EXAMPLE NO. 2, IS THAT ON THE Recent

SECOND INPUT LINE WE HAVE ADDED THE ENERGY RANGE 0.01 TO 0.1 EV. Recent

USE \PREPRO94\LINEAR\ENDFB.OUT AS INPUT AND ENDFB.OUT AS OUTPUT - Recent

SINCE ENDFB.OUT IS THE STANDARD OUTPUT FILENAME THE NAME CAN BE Recent

EITHER INCLUDED IN THE INPUT OR LEFT BLANK. Recent

Recent

THE FOLLOWING 7 INPUT CARDS ARE REQUIRED. Recent

Recent

1 1.00000-08 0 0 0 0 Recent

\PREPRO94\LINEAR\ENDFB.OUT Recent

ENDFB.OUT Recent

92000 92999 1.00000- 2 1.00000- 1 Recent

90232 (UPPER LIMIT AUTOMATICALLY SET TO 90232) Recent

(END REQUEST LIST) Recent

(USE STANDARD OPTION FOR ERROR LAW) Recent

Recent

EXAMPLE INPUT NO. 4 Recent

------------------- Recent

RECONSTRUCT ALL DATA. OUTPUT ALL REACTIONS, REGARDING OF WHETHER Recent

OR NOT THERE IS A BACKGROUND CROSS SECTION. DO NOT MONITOR THE Recent

PROGRESS OF THE PROGRAM. RECONSTRUCT CROSS SECTIONS TO 1 PER-CENT Recent

ACCURACY. USE \ENDFB6\LINEAR\ZA092238 AS INPUT AND Recent

\ENDFB6\RECENT\ZA092238 AS OUTPUT. Recent

Recent

THE FOLLOWING 6 INPUT CARDS ARE REQUIRED. Recent

Recent

0 0.0 1 0 0 0 Recent

\ENDFB6\ZA092238 Recent

\ENDFB6\RECENT\ZA092238 Recent

(RETRIEVE ALL DATA, END REQUEST LIST) Recent

1.00000- 2 Recent

(END FILE 2 ERROR LAW) Recent

Recent

EXAMPLE INPUT NO. 5 Recent

------------------- Recent

RECONSTRUCT ALL DATA. ONLY OUTPUT REACTIONS FOR WHICH A BACKGROUND Recent

CROSS SECTION IS GIVEN. DO NOT MONITOR THE PROGRESS OF THE PROGRAM Recent

RECONSTRUCT CROSS SECTIONS TO 0.1 PER-CENT ACCURACY. USE ENDFB.IN Recent

AS INPUT AND ENDFB.OUT AS OUTPUT. Recent

Recent

THIS CORRESPONDS TO USING ALL OF THE STANDARD OPTONS BUILT-IN TO Recent

THE PROGRAM AND ALL INPUT CARDS MAY BE BLANK. Recent

Recent

IN THIS CASE THE FOLLOWING 5 INPUT CARDS ARE REQUIRED. Recent

(ZEROES ARE INDICATED ON THE FIRST LINE, BELOW, ONLY TO INDICATE Recent

WHERE THE LINE IS. THE ACTUAL INPUT LINE CAN BE COMPLETELY BLANK). Recent

Recent

0 0.0 0 0 0 0 Recent

(USE STANDARD INPUT FILENAME = ENDFB.IN) Recent

(USE STANDARD OUTPUT FILENAME = ENDFB.OUT) Recent

(RETRIEVE ALL DATA, END REQUEST LIST) Recent

(0.1 ERROR, END FILE 2 ERROR LAW) Recent

Recent

======================================================================= Recent

======================================================================= Relabel

Relabel

PROGRAM RELABEL Relabel

VERSION 69-1 (APRIL 1969) Relabel

VERSION 73-1 (JUNE 1973) Relabel

VERSION 77-1 (SEPTEMBER 1977) Relabel

VERSION 80-1 (AUGUST 1980) IBM VERSION Relabel

VERSION 83-1 (JANUARY 1983) COMBINED STATEMENT NUMBER SEQUENCE Relabel

AND LINE I.D. INTO ONE PROGRAM. Relabel

VERSION 86-1 (JANUARY 1986) FORTRAN-77/H VERSION Relabel

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Relabel

FILE NAMES (SEE, SUBROUTINES FILIO1 Relabel

AND FILIO2 FOR DETAILS). Relabel

*IMPROVED BASED ON USER COMMENTS. Relabel

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Relabel

INSURE PROGRAM WILL NOT DO ANYTHING Relabel

CRAZY. Relabel

*UPDATED TO USE NEW PROGRAM CONVERT Relabel

KEYWORDS. Relabel

*ADDED LIVERMORE CIVIC COMPILER Relabel

CONVENTIONS. Relabel

VERSION 92-1 (JANUARY 1992)*ADDED FORTRAN SAVE OPTION Relabel

VERSION 94-1 (JANUARY 1994)*COMPLETE RE-WRITE Relabel

*OUTPUT MINIMUM NON-BLANK LENGTH FOR Relabel

EACH LINE - NO SEQUENCE NUMBERS. Relabel

*INCREASED MAXIMUM NUMBER OF LABELS Relabel

PER ROUTINE FROM 1000 TO 50,000 Relabel

*CAN NOW PROCESS UPPER OR LOWER CASE Relabel

CODING. Relabel

*SKIP IMBEDDED BLANKS IN KEYWORDS. Relabel

*ADDED WRITE(XX,XX,ERR=YYY,END=ZZZ) Relabel

*ADDED OPEN(XX,ERR=YYY,END=ZZZ) Relabel

*ADDED CLOSE(XX,ERR=YYY,END=ZZZ) Relabel

*INTEGER INSTEAD OF CHARACTERS IS NO Relabel

LONGER SUPPORTED - ALL CHARACTERS Relabel

MUST BE IDENTIFIED AS CHARACTERS. Relabel

*VARIABLE FILENAMES TO ALLOW ACCESS Relabel

FILE STRUCTURES Relabel

(WARNING - INPUT PARAMETER FORMAT Relabel

HAS BEEN CHANGED) Relabel

*CLOSE ALL FILES BEFORE TERMINATING Relabel

(SEE, SUBROUTINE ENDIT) Relabel

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Relabel

*IMPROVED COMPUTER INDEPENDENCE Relabel

*ALL DOUBLE PRECISION Relabel

*ON SCREEN OUTPUT Relabel

*IMPROVED OUTPUT PRECISION Relabel

*DEFINED SCRATCH FILE NAMES Relabel

*INCREASED THE NUMBER OF LABELS Relabel

IN A ROUTINE FOR 5,000 TO 50,000 Relabel

VERSION 99-1 (MARCH 1999) *GENERAL IMPROVEMENTS BASED ON Relabel

USER FEEDBACK Relabel

VERS. 2000-1 (FEBRUARY 2000)*UPDATED TO IGNORE ( AND ) IN QUOTES Relabel

*GENERAL IMPROVEMENTS BASED ON Relabel

USER FEEDBACK Relabel

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Relabel

*CORRECTED END=, ERR=, WHEN I/O UNIT Relabel

NUMBER IS DIMENSIONED Relabel

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Relabel

*INCREASED THE NUMBER OF LABELS IN Relabel

A ROUTINE FOR 50,000 TO 100,000 Relabel

Relabel

OWNED, MAINTAINED AND DISTRIBUTED BY Relabel

------------------------------------ Relabel

THE NUCLEAR DATA SECTION Relabel

INTERNATIONAL ATOMIC ENERGY AGENCY Relabel

P.O. BOX 100 Relabel

A-1400, VIENNA, AUSTRIA Relabel

EUROPE Relabel

Relabel

ORIGINALLY WRITTEN BY Relabel

------------------------------------ Relabel

DERMOTT E. CULLEN Relabel

UNIVERSITY OF CALIFORNIA Relabel

LAWRENCE LIVERMORE NATIONAL LABORATORY Relabel

L-159 Relabel

P.O. BOX 808 Relabel

LIVERMORE, CA 94550 Relabel

U.S.A. Relabel

TELEPHONE 925-423-7359 Relabel

E. MAIL CULLEN1@LLNL.GOV Relabel

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Relabel

Relabel

PURPOSE Relabel

------- Relabel

THIS PROGRAM IS DESIGNED TO RE-LABEL A FORTRAN PROGRAM SO THAT Relabel

STATEMENT LABELS ARE IN INCREASING ORDER IN INCREMENTS OF 10 Relabel

WITHIN EACH ROUTINE. Relabel

Relabel

THE FOLLOWING TYPES OF FORTRAN STATEMENTS ARE CONSIDERED, Relabel

Relabel

GO TO NN Relabel

GO TO (NN,MM,.....,JJ,KK),LL (MULTI LINE O.K.) Relabel

DO NN Relabel

IF(......) NN,MM,...JJ,KK Relabel

IF(......) GO TO NN Relabel

IF(......) GO TO (NN,MM,.....,JJ,KK),LL (MULTI LINE O.K.) Relabel

IF(......) READ(.....,END=NN,ERR=MM) Relabel

IF(......) WRITE(.....,END=NN,ERR=MM) Relabel

READ(......,END=NN,ERR=MM) Relabel

OPEN(......,END=NN,ERR=MM) Relabel

Relabel

GO TO STATEMENTS MAY APPEAR IN THE FORM 'GO TO' OR 'GOTO'. IF Relabel

THERE IS ROOM ON THE LINE 'GOTO' WILL BE CONVERTED TO 'GO TO'. Relabel

WHETHER OR NOT 'GOTO' IS CONVERTED TO 'GO TO' IT WILL BE TREATED Relabel

AS IDENTICAL TO 'GO TO' FOR SUBSEQUENT PROCESSING AND RELACEMENT Relabel

OF STATEMENT NUMBERS. Relabel

Relabel

ALL OTHER STATEMENT TYPES ARE NOT CHANGED. IN PARTICULAR ALL I/O Relabel

STATEMENTS AND ASSOCIATED FORMAT STATEMENTS ARE NOT CONVERTED. Relabel

Relabel

WARNING Relabel

------- Relabel

THIS PROGRAM IS ONLY DESIGNED TO MAINTAIN ENDF/B PRE-PROCESSING Relabel

PROGRAMS, WHICH ONLY USE A RESTRICTED SET OF FORTRAN STATEMENT Relabel

TYPES THAT CAN BE USED ON A VARIETY OF DIFFERENT TYPES OF Relabel

COMPUTERS. THIS PROGRAM IS NOT DESIGNED TO HANDLE ALL POSSIBLE Relabel

TYPES OF FORTRAN STATEMENTS. Relabel

Relabel

THE FORTRAN STATEMENTS DESCRIBED ABOVE AND TREATED BY THIS PROGRAM Relabel

DO NOT INCLUDE ALL POSSIBLE FORTRAN STATEMENTS. AS SUCH THIS Relabel

PROGRAM IS NOT COMPLETELY GENERAL AND SHOULD ONLY BE USED WITH Relabel

PROGRAMS THAT ONLY USE THE FORTRAN STATEMENTS DESCRIBED ABOVE. Relabel

Relabel

FAILURE TO FOLLOW THESE INSTRUCTIONS CAN LEAD TO ERROR IN PROGRAMS Relabel

Relabel

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINES FILIO1 AND FILIO2) Relabel

---------------------------------------------------------------- Relabel

UNIT FILE NAME DESCRIPTION Relabel

---- ---------- ----------- Relabel

2 RELABEL.INP INPUT PARAMETERS Relabel

3 RELABEL.LST OUTPUT REPORT Relabel

10 RELABEL.IN PROGRAM TO READ Relabel

11 RELABEL.OUT PROGRAM TO WRITE Relabel

12 (SCRATCH) Relabel

Relabel

INPUT CARDS Relabel

----------- Relabel

LINE COLUMNS DEFINITION Relabel

---- ------- ---------- Relabel

1 1-60 INPUT PROGRAM FILENAME Relabel

(STANDARD OPTION = RELABEL.IN) Relabel

2 1-60 OUTPUT PROGRAM FILENAME Relabel

(STANDARD OPTION = RELABEL.OUT) Relabel

Relabel

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Relabel

THEN USE STANDARD FILENAMES. Relabel

Relabel

EXAMPLE INPUT NO. 1 Relabel

------------------- Relabel

TO READ \PREPRO94\RECENT\RECENT.FOR AND Relabel

WRITE \PREPRO94\RECENT\RECENT.NEW THE FOLLOWING 2 INPUT LINES Relabel

ARE REQUIRED, Relabel

Relabel

\PREPRO94\RECENT\RECENT.FOR Relabel

Relabel

EXAMPLE INPUT NO. 2 Relabel

------------------- Relabel

TO READ RELABEL.IN AND WRITE RELABEL.OUT THE FOLOWING 2 INPUT Relabel

LINES ARE REQUIRED, Relabel

Relabel

RELABEL.IN Relabel

RELABEL.OUT Relabel

Relabel

EXAMPLE INPUT NO. 3 Relabel

------------------- Relabel

TO READ RELABEL.IN AND WRITE RELABEL.OUT, SINCE THESE ARE THE Relabel

STANDARD OPTIONS THE 2 INPUT LINES CAN BE COMPLETELY BLANK. Relabel

Relabel

======================================================================= Relabel

======================================================================= Sigma1

Sigma1

PROGRAM SIGMA1 Sigma1

============== Sigma1

VERSION 73-1 (MARCH 1973) Sigma1

VERSION 76-1 (FEBRUARY 1976) Sigma1

VERSION 76-2 (OCTOBER 1976) Sigma1

VERSION 77-1 (JANUARY 1977) Sigma1

VERSION 78-1 (JULY 1978) Sigma1

VERSION 79-1 (JULY 1979) CDC-7600 AND CRAY-1 VERSION. Sigma1

VERSION 80-1 (MAY 1980) IBM, CDC AND CRAY VERSION Sigma1

VERSION 80-2 (DECEMBER 1980)IMPROVED BASED ON USER COMMENTS. Sigma1

VERSION 81-1 (MARCH 1981) DOUBLE PRECISION IBM VERSION Sigma1

VERSION 81-2 (AUGUST 1981) IMPROVED IBM SPEED AND STABILITY Sigma1

VERSION 82-1 (JANUARY 1982) IMPROVED COMPUTER COMPATIBILITY Sigma1

VERSION 83-1 (JANUARY 1983)*MAJOR RE-DESIGN. Sigma1

*PAGE SIZE INCREASED - 1002 TO 2004. Sigma1

*ELIMINATED COMPUTER DEPENDENT CODING. Sigma1

*NEW, MORE COMPATIBLE I/O UNIT NUMBER. Sigma1

*ADDED STANDARD ALLOWABLE ERROR OPTION Sigma1

(CURRENTLY 0.1 PER-CENT). Sigma1

*UNRESOLVED RESONANCE REGION COPIED. Sigma1

*1/V EXTENSION OF CROSS SECTIONS Sigma1

OUTSIDE OF TABULATED ENERGY RANGE AND Sigma1

INTO UNRESOLVED ENERGY RANGE. Sigma1

VERSION 83-2 (OCTOBER 1983)*IMPROVED BASED ON USER COMMENTS. Sigma1

VERSION 84-1 (APRIL 1984) *IMPROVED NUMERICAL STABILITY. Sigma1

*PARTIAL EVALUATION TREATMENT. Sigma1

VERSION 85-1 (APRIL 1985) *ITERATE TO CONVERGENCE (USING THE SAME Sigma1

ENERGY GRID FOR HOT CROSS SECTION AS Sigma1

COLD CROSS SECTIONS WAS FOUND TO BE Sigma1

INACCURATE). Sigma1

*NEW FASTER HIGH ENERGY BROADENING. Sigma1

*UPDATED FOR ENDF/B-VI FORMATS. Sigma1

*SPECIAL I/O ROUTINES TO GUARANTEE Sigma1

ACCURACY OF ENERGY. Sigma1

*DOUBLE PRECISION TREATMENT OF ENERGY Sigma1

(REQUIRED FOR NARROW RESONANCES). Sigma1

VERSION 85-2 (AUGUST 1985) *FORTRAN-77/H VERSION Sigma1

VERSION 86-1 (JANUARY 1986)*ENERGY DEPENDENT SCATTERING RADIUS Sigma1

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Sigma1

FILE NAMES (SEE, SUBROUTINE FILEIO Sigma1

FOR DETAILS). Sigma1

*IMPROVED BASED ON USER COMMENTS. Sigma1

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Sigma1

INSURE PROGRAM WILL NOT DO ANYTHING Sigma1

CRAZY. Sigma1

*UPDATED TO USE NEW PROGRAM CONVERT Sigma1

KEYWORDS. Sigma1

*ADDED LIVERMORE CIVIC COMPILER Sigma1

CONVENTIONS. Sigma1

VERSION 90-1 (JUNE 1990) *UPDATED BASED ON USER COMMENTS Sigma1

*ADDED FORTRAN SAVE OPTION Sigma1

*NEW MORE CONSISTENT ENERGY OUTPUT Sigma1

ROUTINES Sigma1

VERSION 91-1 (JULY 1991) *WARNING...INPUT PARAMETER FORMAT Sigma1

HAS BEEN CHANGED - SEE BELOW FOR Sigma1

DETAILS. Sigma1

*ADDED CHARGED PARTICLE PROJECTILES Sigma1

*OUTPUT ENERGY RANGE IS ALWAYS AT Sigma1

LEAST AS LARGE AS INPUT ENERGY RANGE. Sigma1

*NO 1/V EXTENSION OF CROSS SECTIONS Sigma1

FROM UNRESOLVED ENERGY RANGE. Sigma1

VERSION 92-1 (JANUARY 1992)*INSURE MINIMUM AND MAXIMUM CROSS Sigma1

SECTIONS ARE ALWAYS KEPT (NOT THINNED) Sigma1

*MT=19 (FIRST CHANCE FISSION) TREATED Sigma1

THE SAME AS FISSION. Sigma1

*VARIABLE MINIMUM CROSS SECTION OF Sigma1

INTEREST - TO ALLOW SMALL CROSS Sigma1

SECTIONS NEAR THRESHOLDS TO BE Sigma1

TREATED PROPERLY. Sigma1

*ALL ENERGIES INTERNALLY ROUNDED PRIOR Sigma1

TO CALCULATIONS. Sigma1

*COMPLETELY CONSISTENT I/O AND ROUNDING Sigma1

ROUTINES - TO MINIMIZE COMPUTER Sigma1

DEPENDENCE. Sigma1

VERSION 92-2 (JULY 1992) *CORRECTED BUG ASSOCIATED WITH Sigma1

THRESHOLD REACTIONS. Sigma1

*UNRESOLVED REGION COPIED WITHOUT Sigma1

THINNING (IT SHOULD BE EXACTLY THE Sigma1

SAME AT ALL TEMPERATURES). Sigma1

*NO THINNING OF REACTIONS (MT) THAT Sigma1

WERE NOT BROADENED. Sigma1

VERSION 93-1 (APRIL 1993) *INCREASED PAGE SIZE FROM 2004 Sigma1

TO 24000 ENERGY PONTS. Sigma1

VERSION 94-1 (JANUARY 1994)*VARIABLE ENDF/B DATA FILENAMES Sigma1

TO ALLOW ACCESS TO FILE STRUCTURES Sigma1

(WARNING - INPUT PARAMETER FORMAT Sigma1

HAS BEEN CHANGED) Sigma1

*CLOSE ALL FILES BEFORE TERMINATING Sigma1

(SEE, SUBROUTINE ENDIT) Sigma1

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Sigma1

*IMPROVED COMPUTER INDEPENDENCE Sigma1

*ALL DOUBLE PRECISION Sigma1

*ON SCREEN OUTPUT Sigma1

*UNIFORM TREATMENT OF ENDF/B I/O Sigma1

*IMPROVED OUTPUT PRECISION Sigma1

*DEFINED SCRATCH FILE NAMES Sigma1

*ALWAYS INCLUDE THERMAL VALUE Sigma1

VERSION 97-1 (APRIL 1997) *OPTIONALLY SET NEGATIVE CROSS Sigma1

SECTIONS = 0 ON INPUT AND Sigma1

OUTPUT. Sigma1

*INCREASED PAGE SIZE FROM 24000 Sigma1

TO 60000 ENERGY POINTS. Sigma1

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Sigma1

POINT READ FOR MORE DIGITS Sigma1

*UPDATED TEST FOR ENDF/B FORMAT Sigma1

VERSION BASED ON RECENT FORMAT CHANGE Sigma1

*TREAT LOW ENERGY INITIAL CROSS Sigma1

SECTIONS AS LOG-LOG INTERPOLABLE Sigma1

*CONSTANT (RATHER THAN 1/V) EXTENSION Sigma1

TO HIGHER ENERGY. Sigma1

*UPDATED CONSTANTS BASED ON CSEWG Sigma1

SUBCOMMITTEE RECOMMENDATIONS Sigma1

*GENERAL IMPROVEMENTS BASED ON Sigma1

USER FEEDBACK Sigma1

VERSION 99-2 (JUNE 1999) *EXTENDED RANGE OF INTEGRALS FROM 4 Sigma1

TO 5 UNITS ON EACH SIDE OF ENERGY Sigma1

POINT TO ALLOW FOR LARGER VARIATION Sigma1

IN THE LOCAL CROSS SECTION Sigma1

*ASSUME ENDF/B-VI, NOT V, IF MISSING Sigma1

MF=1, MT-451. Sigma1

VERSION 99-3 (OCTOBER 1999))*IMPROVED ERFC FUNCTION DEFINITION. Sigma1

I THANK BOB MACFARLANE (LANL) FOR Sigma1

SUPPLYING A MORE ACCURATE ERFC Sigma1

FUNCTION. Sigma1

VERS. 2000-1 (FEBRUARY 2000)*CORRECTED LOW ENERGY INTERPOLATION Sigma1

FOR NON-POSITIVE CROSS SECTIONS Sigma1

*GENERAL IMPROVEMENTS BASED ON Sigma1

USER FEEDBACK Sigma1

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Sigma1

VERS. 2004-1 (JAN. 2004) *OPTIONALLY IGNORE UNRESOLVED REGION Sigma1

*CORRECTED PROBLEM AT THE RESOLVED/ Sigma1

UNRESOLVED ENERGY BOUNDARY. Sigma1

*CORRECTED HIGH ENERGY CONSTANT CROSS Sigma1

SECTION EXTENSION. Sigma1

*TIGHTER CRITERIA FOR INITIAL ENERGY Sigma1

POINT SPACING Sigma1

*TEMPERATURE DEPENDENT ENERGY POINT Sigma1

SPACING. Sigma1

*ADDED NEW REICH-MOORE (LRF=7) TO Sigma1

FILE2 TO ALLOW COPY TO FIND ANY Sigma1

FOLLOWING UNRESOLVED PARAMETERS Sigma1

Sigma1

Acknowledgement 2004 Sigma1

-------------------- Sigma1

Currently almost all improvements to this code are based upon Sigma1

feedback from code users who report problems. This feedback Sigma1

benefits ALL users of this code, and ALL users are encouraged Sigma1

to report problems. Sigma1

Sigma1

Improvements on the 2004 version of this code based on user Sigma1

feedback including, Sigma1

1) Bret Beck - reported a problem at the resolved/unresolved Sigma1

energy boundary. Sigma1

2) S. Ganesan - reported a problem for small temperature changes. Sigma1

Sigma1

OWNED, MAINTAINED AND DISTRIBUTED BY Sigma1

------------------------------------ Sigma1

THE NUCLEAR DATA SECTION Sigma1

INTERNATIONAL ATOMIC ENERGY AGENCY Sigma1

P.O. BOX 100 Sigma1

A-1400, VIENNA, AUSTRIA Sigma1

EUROPE Sigma1

Sigma1

ORIGINALLY WRITTEN BY Sigma1

------------------------------------ Sigma1

DERMOTT E. CULLEN Sigma1

UNIVERSITY OF CALIFORNIA Sigma1

LAWRENCE LIVERMORE NATIONAL LABORATORY Sigma1

L-159 Sigma1

P.O. BOX 808 Sigma1

LIVERMORE, CA 94550 Sigma1

U.S.A. Sigma1

TELEPHONE 925-423-7359 Sigma1

E. MAIL CULLEN1@LLNL.GOV Sigma1

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Sigma1

Sigma1

AUTHORS MESSAGE Sigma1

--------------- Sigma1

THE REPORT DESCRIBED ABOVE IS THE LATEST PUBLISHED DOCUMENTATION Sigma1

FOR THIS PROGRAM. HOWEVER, THE COMMENTS BELOW SHOULD BE CONSIDERED Sigma1

THE LATEST DOCUMENTATION INCLUDING ALL RECENT IMPROVEMENTS. PLEASE Sigma1

READ ALL OF THESE COMMENTS BEFORE IMPLEMENTATION, PARTICULARLY Sigma1

THE COMMENTS CONCERNING MACHINE DEPENDENT CODING. Sigma1

Sigma1

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Sigma1

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Sigma1

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Sigma1

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Sigma1

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Sigma1

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Sigma1

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Sigma1

COMPUTER. Sigma1

Sigma1

PURPOSE Sigma1

------- Sigma1

THIS PROGRAM IS DESIGNED TO DOPPLER BROADEN NEUTRON INDUCED Sigma1

CROSS SECTIONS. EACH SECTION OF CROSS SECTIONS (FILE 3) IS READ Sigma1

FROM THE ENDF/B FORMAT. THE DATA IS DOPPLER BROADENED, THINNED Sigma1

AND OUTPUT IN THE ENDF/B FORMAT. Sigma1

Sigma1

IN THE FOLLOWING DISCUSSION FOR SIMPLICITY THE ENDF/B TERMINOLOGY Sigma1

---ENDF/B TAPE---WILL BE USED. IN FACT THE ACTUAL MEDIUM MAY BE Sigma1

TAPE, CARDS, DISK OR ANY OTHER MEDIUM. Sigma1

Sigma1

ENDF/B FORMAT Sigma1

------------- Sigma1

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Sigma1

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Sigma1

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II, III, IV OR V FORMAT). Sigma1

Sigma1

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Sigma1

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Sigma1

ASSUMED THAT THE MAT, MF AND MT ON EACH CARD IS CORRECT. SEQUENCE Sigma1

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Sigma1

CORRECTLY OUTPUT ON ALL CARDS. THE FORMAT OF SECTION MF=1, MT=451 Sigma1

AND ALL SECTIONS OF MF=3 MUST BE CORRECT. THE PROGRAM COPIES ALL Sigma1

OTHER SECTION OF DATA AS HOLLERITH AND AS SUCH IS INSENSITIVE TO Sigma1

THE CORRECTNESS OR INCORRECTNESS OF ALL OTHER SECTIONS. Sigma1

Sigma1

ALL CROSS SECTIONS THAT ARE USED BY THIS PROGRAM MUST BE TABULATED Sigma1

AND LINEARLY INTERPOLABLE IN ENERGY AND CROSS SECTION (ENDF/B Sigma1

INTERPOLATION LAW 2). FILE 3 CROSS SECTIONS MAY BE MADE LINEARLY Sigma1

INTERPOLABLE BY USING PROGRAM LINEAR (UCRL-50400, VOL.17, PART A). Sigma1

FILE 2 RESONANCE PARAMETERS MAY BE USED TO RECONSTRUCT ENERGY Sigma1

DEPENDENT CROSS SECTIONS AND ADD IN FILE 3 BACKGROUND CROSS Sigma1

SECTIONS TO DEFINE LINEARLY INTERPOLABLE CROSS SECTIONS BY USING Sigma1

PROGRAM RECENT (UCRL-50400, VOL. 17, PART C). IF THIS PROGRAM Sigma1

FINDS THAT THE FILE 3 CROSS SECTIONS ARE NOT LINEARLY INTERPOLABLE Sigma1

THIS PROGRAM WILL TERMINATE EXECUTION. Sigma1

Sigma1

UNRESOLVED RESONANCE REGION Sigma1

--------------------------- Sigma1

IN THE UNRESOLVED RESONANCE REGION IT IS NOT POSSIBLE TO EXACTLY Sigma1

DEFINE THE ENERGY DEPENDENCE OF THE CROSS SECTIONS. THE AVERAGE Sigma1

WIDTHS AND SPACINGS GIVEN IN ENDF/B ARE ONLY ADEQUATE TO DEFINE Sigma1

AVERAGE VALUES OF THE CROSS SECTIONS. THEREFORE ALL CROSS SECTIONS Sigma1

IN THE ENDF/B FORMAT FOR THE UNRESOLVED REGION ARE REALLY AVERAGE Sigma1

VALUES WHICH CANNOT BE DOPPLER BROADENED USING THE SIGMA1 METHOD Sigma1

(WHICH REQUIRES TABULATED, LINEARLY INTERPOLABLE, ENERGY DEPENDENT Sigma1

CROSS SECTIONS. Sigma1

Sigma1

THEREFORE, Sigma1

(1) ALL TABULATED POINTS WITHIN THE UNRESOLVED RESONANCE REGION Sigma1

WILL BE COPIED, WITHOUT MODIFICATION OR BROADENING. ADOPTION OF Sigma1

THIS CONVENTION WILL ALLOW SUBSEQUENT PROGRAMS TO PROPERLY DEFINE Sigma1

SELF-SHIELDED, DOPPLER BROADENED CROSS SECTIONS IN THE UNRESOLVED Sigma1

RESONANCE REGION. Sigma1

(2) CROSS SECTIONS WILL BE EXTENDED AS 1/V ABOVE THE UPPER ENERGY Sigma1

LIMIT OF THE RESOLVED RESONANCE REGION AND BELOW THE LOWER ENERGY Sigma1

LIMIT OF THE CONTINUUUM REGION (I.E. INTO THE UNRESOLVED Sigma1

RESONANCE REGION). THIS CONVENTION WILL GUARANTEE A SMOOTH Sigma1

BEHAVIOR CLOSE TO THE UNRESOLVED RESONANCE REGION BOUNDARIES. Sigma1

Sigma1

OUTPUT FORMAT Sigma1

------------- Sigma1

IN THIS VERSION OF SIGMA1 ALL FILE 3 ENERGIES WILL BE OUTPUT IN Sigma1

F (INSTEAD OF E) FORMAT IN ORDER TO ALLOW ENERGIES TO BE WRITTEN Sigma1

WITH UP TO 9 DIGITS OF ACCURACY. IN PREVIOUS VERSIONS THIS WAS AN Sigma1

OUTPUT OPTION. HOWEVER USE OF THIS OPTION TO COMPARE THE RESULTS Sigma1

OF ENERGIES WRITTEN IN THE NORMAL ENDF/B CONVENTION OF 6 DIGITS Sigma1

TO THE 9 DIGIT OUTPUT FROM THIS PROGRAM DEMONSTRATED THAT FAILURE Sigma1

TO USE THE 9 DIGIT OUTPUT CAN LEAD TO LARGE ERRORS IN THE DATA Sigma1

JUST DUE TO TRANSLATION OF THE ENERGIES TO THE ENDF/B FORMAT. Sigma1

Sigma1

CONTENTS OF OUTPUT Sigma1

------------------ Sigma1

ENTIRE EVALUATIONS ARE OUTPUT, NOT JUST THE BROADENED FILE 3 Sigma1

CROSS SECTIONS, E.G. ANGULAR AND ENERGY DISTRIBUTIONS ARE ALSO Sigma1

INCLUDED. Sigma1

Sigma1

DOCUMENTATION Sigma1

------------- Sigma1

THE FACT THAT THIS PROGRAM HAS OPERATED ON THE DATA IS DOCUMENTED Sigma1

BY THE ADDITION OF THREE COMMENTS CARDS AT THE END OF EACH Sigma1

HOLLERITH SECTION IN THE FORM Sigma1

Sigma1

***************** PROGRAM SIGMA1 (2004-1) *************** Sigma1

DATA DOPPLER BROADENED TO 300.0 KELVIN AND Sigma1

DATA THINNED TO WITHIN AN ACCURACY OF 0.1 PER-CENT Sigma1

Sigma1

THE ORDER OF ALL SIMILAR COMMENTS (FROM LINEAR,RECENT AND GROUPY) Sigma1

REPRESENTS A COMPLETE HISTORY OF ALL OPERATIONS PERFORMED ON Sigma1

THE DATA. Sigma1

Sigma1

THESE COMMENT CARDS ARE ONLY ADDED TO EXISTING HOLLERITH SECTIONS, Sigma1

I.E., THIS PROGRAM WILL NOT CREATE A HOLLERITH SECTION. THE FORMAT Sigma1

OF THE HOLLERITH SECTION IN ENDF/B-V DIFFERS FROM THE THAT OF Sigma1

EARLIER VERSIONS OF ENDF/B. BY READING AN EXISTING MF=1, MT=451 Sigma1

IT IS POSSIBLE FOR THIS PROGRAM TO DETERMINE WHICH VERSION OF Sigma1

THE ENDF/B FORMAT THE DATA IS IN. WITHOUT HAVING A SECTION OF Sigma1

MF=1, MT=451 PRESENT IT IS IMPOSSIBLE FOR THIS PROGRAM TO Sigma1

DETERMINE WHICH VERSION OF THE ENDF/B FORMAT THE DATA IS IN, AND Sigma1

AS SUCH IT IS IMPOSSIBLE FOR THE PROGRAM TO DETERMINE WHAT FORMAT Sigma1

SHOULD BE USED TO CREATE A HOLLERITH SECTION. Sigma1

Sigma1

REACTION INDEX Sigma1

-------------- Sigma1

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Sigma1

SECTION MF=1, MT=451 OF EACH EVALUATION. Sigma1

Sigma1

THIS PROGRAM DOES NOT UPDATE THE REACTION INDEX IN MF=1, MT=451. Sigma1

THIS CONVENTION HAS BEEN ADOPTED BECAUSE MOST USERS DO NOT Sigma1

REQUIRE A CORRECT REACTION INDEX FOR THEIR APPLICATIONS AND IT WAS Sigma1

NOT CONSIDERED WORTHWHILE TO INCLUDE THE OVERHEAD OF CONSTRUCTING Sigma1

A CORRECT REACTION INDEX IN THIS PROGRAM. HOWEVER, IF YOU REQUIRE Sigma1

A REACTION INDEX FOR YOUR APPLICATIONS, AFTER RUNNING THIS PROGRAM Sigma1

YOU MAY USE PROGRAM DICTIN TO CREATE A CORRECT REACTION INDEX. Sigma1

Sigma1

SECTION SIZE Sigma1

------------ Sigma1

SINCE THIS PROGRAM USES A LOGICAL PAGING SYSTEM THERE IS NO LIMIT Sigma1

TO THE NUMBER OF POINTS IN ANY SECTION, E.G., THE TOTAL CROSS Sigma1

SECTION MAY BE REPRESENTED BY 200,000 DATA POINTS. Sigma1

Sigma1

SELECTION OF DATA Sigma1

----------------- Sigma1

THE PROGRAM SELECTS MATERIALS TO BE BROADENED BASED EITHER ON Sigma1

MAT (ENDF/B MAT NO.) OR ZA. THE PROGRAM ALLOWS UP TO 100 MAT OR Sigma1

ZA RANGES TO BE SPECIFIED. THE PROGRAM WILL ASSUME THAT THE Sigma1

ENDF/B TAPE IS IN EITHER MAT OR ZA ORDER, WHICHEVER CRITERIA IS Sigma1

USED TO SELECT MATERIALS, AND WILL TERMINATE WHEN A MAT OR ZA Sigma1

IS FOUND THAT IS ABOVE THE RANGE OF ALL REQUESTS. Sigma1

Sigma1

ENERGY GRID OF BROADENED DATA Sigma1

----------------------------- Sigma1

THE ENERGY GRID FOR THE DOPPLER BROADENED CROSS SECTIONS IS Sigma1

SELECTED TO INSURE THAT THE BROADENED DATA IS LINEAR-LINEAR Sigma1

INTERPOLABLE. AS SUCH THE ENERGY GRID FOR THE BROADENED DATA Sigma1

MAY NOT BE THE SAME AS THE ENERGY GRID FOR THE ORIGINAL Sigma1

UNBROADENED DATA. GENERALLY AFTER BROADENING THERE WILL BE Sigma1

FEWER DATA POINTS IN THE RESONANCE REGION, BUT AT LOW ENERGY Sigma1

THERE MAY BE MORE POINTS, DUE TO THE 1/V LOW ENERGY EFFECT Sigma1

CREATED BY DOPPLER BROADENING. Sigma1

Sigma1

EFFECTIVE TEMERATURE INCREASE Sigma1

----------------------------- Sigma1

IF THE ORIGINAL DATA IS NOT AT ZERO KELVIN THE PROGRAM WILL Sigma1

BROADEN THE DATA BY THE EFFECTIVE TEMPERATURE DIFFENCE TO THE Sigma1

FINAL TEMPERATURE. IF THE DATA IS ALREADY AT A TEMPERATURE THAT Sigma1

IS HIGHER THAN THE FINAL TEMPERATURE DOPPLER BROADENING IS Sigma1

NATURALLY NOT PERFORMED AND THE TEMPERATURE IN THE SECTION IS LEFT Sigma1

AT ITS ORIGINAL VALUE. Sigma1

Sigma1

MULTIPLE FINAL TEMPERATURES Sigma1

--------------------------- Sigma1

THE PRESENT VERSION ONLY DOPPLER BROADENS TO ONE FINAL TEMPERATURE Sigma1

(IF THERE IS SUFFICIENT INTEREST EXPRESSED BY USERS FUTURE Sigma1

VERSION MAY BROADEN TO MULTIPLE TEMPERATURES. PLEASE Sigma1

CONTACT THE AUTHOR IF YOU ARE INTERESTED IN A MULTIPLE Sigma1

TEMPERATURE OPTION). Sigma1

Sigma1

PROGRAM OPERATION Sigma1

----------------- Sigma1

EACH SECTION OF FILE 3 DATA IS CONSIDERED SEPERATELY. THE DATA Sigma1

IS READ AND DOPPLER BROADENED A PAGE AT A TIME (ONE PAGE IS Sigma1

60000 DATA POINTS). UP TO THREE PAGES OF DATA MAY BE IN THE CORE Sigma1

AT ANY GIVEN TIME, THE PAGE BEING BROADENED, THE PAGE BELOW IT Sigma1

IN ENERGY AND THE PAGE ABOVE IT IN ENERGY. AFTER A PAGE HAS BEEN Sigma1

BROADENED IT IS THINNED, IF THE ENTIRE SECTION CONTAINS ONLY Sigma1

ONE PAGE OR LESS, IT WILL STILL BE CORE RESIDENT AND WILL BE Sigma1

WRITTEN DIRECTLY FROM CORE TO THE OUTPUT TAPE. IF THE BROADENED, Sigma1

THINNED SECTION IS LARGER THAN A PAGE, AFTER A PAGE HAS BEEN Sigma1

BROADENED AND THINNED IT IS WRITTEN TO A SCRATCH FILE. AFTER THE Sigma1

ENTIRE SECTION HAS BEEN BROADENED AND THINNED THE DATA IS READ Sigma1

FROM SCRATCH TO CORE, ONE PAGE AT A TIME, THE OUTPUT TO THE OUTPUT Sigma1

TAPE. Sigma1

Sigma1

ALLOWABLE ERROR Sigma1

--------------- Sigma1

AFTER DOPPLER BROADENING THE CROSS SECTION IN THE RESONANCE REGION Sigma1

WILL GENERALLY BE MUCH SMOOTHER THAN THE UNBROADENED DATA AND CAN Sigma1

BE REPRESENTED TO THE SAME ACCURACY BY A SMALLER NUMBER OF ENERGY Sigma1

POINTS. THEREFORE AFTER DOPPLER BROADENING THE DATA CAN BE THINNED Sigma1

WITH ESSENTIALLY NO LOSE OF INFORMATION. Sigma1

Sigma1

THE ALLOWABLE ERROR MAY BE ENERGY INDEPENDENT (CONSTANT) OR ENERGY Sigma1

DEPENDENT. THE ALLOWABLE ERROR IS DESCRIBED BY A TABULATED Sigma1

FUNCTION OF UP TO 20 (ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Sigma1

BETWEEN TABULATED POINTS. IF ONLY ONE TABULATED POINT IS GIVEN THE Sigma1

ERROR WILL BE CONSIDERED CONSTANT OVER THE ENTIRE ENERGY RANGE. Sigma1

WITH THIS ENERGY DEPENDENT ERROR ONE MAY OPTIMIZE THE OUTPUT FOR Sigma1

ANY GIVEN APPLICATION BY USING A SMALL ERROR IN THE ENERGY RANGE Sigma1

OF INTEREST AND A LESS STRINGENT ERROR IN OTHER ENERGY RANGES. Sigma1

Sigma1

INPUT FILES Sigma1

----------- Sigma1

UNIT DESCRIPTION Sigma1

---- ----------- Sigma1

2 INPUT CARDS (BCD - 80 CHARACTERS/RECORD) Sigma1

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Sigma1

Sigma1

OUTPUT FILES Sigma1

------------ Sigma1

UNIT DESCRIPTION Sigma1

---- ----------- Sigma1

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Sigma1

11 FINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Sigma1

Sigma1

SCRATCH FILES Sigma1

------------- Sigma1

UNIT DESCRIPTION Sigma1

---- ----------- Sigma1

12 SCRATCH FILE FOR BROADENED DATA Sigma1

(BINARY - 180000 WORDS/RECORD - DOUBLE PRECISION/ Sigma1

42000 WORDS/RECORD - SINLGE PRECISION) Sigma1

Sigma1

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILEIO) Sigma1

---------------------------------------------------- Sigma1

UNIT FILE NAME Sigma1

---- ---------- Sigma1

2 SIGMA1.INP Sigma1

3 SIGMA1.LST Sigma1

10 ENDFB.IN Sigma1

11 ENDFB.OUT Sigma1

12 (SCRATCH) Sigma1

Sigma1

INPUT CARDS Sigma1

----------- Sigma1

CARD COLS. DESCRIPTION Sigma1

---- ----- ----------- Sigma1

1 1-11 SELECTION CRITERIA (0=MAT, 1=ZA) Sigma1

12-22 MONITOR MODE SELECTOR Sigma1

= 0 - NORMAL OPERATION Sigma1

= 1 - MONITOR PROGRESS OF DOPPLER BROADENING OF DATA. Sigma1

EACH TIME A PAGE OF DATA POINTS IS WRITTEN TO Sigma1

THE SCRATCH FILE PRINT OUT THE TOTAL NUMBER OF Sigma1

POINTS ON SCRATCH AND THE LOWER AND UPPER Sigma1

ENERGY LIMITS OF THE PAGE (THIS OPTION MAY BE Sigma1

USED IN ORDER TO MONITOR THE EXECUTION SPEED Sigma1

OF LONG RUNNING JOBS). Sigma1

23-33 KELVIN TEMPERATURE Sigma1

34-44 MINIMUM CROSS SECTION OF INTEREST Sigma1

(DEFAULT VALUE = 1.0E-10 BARNS). Sigma1

45-55 NEGATIVE CROSS SECTION TREATMENT Sigma1

= 0 - O.K. Sigma1

= 1 - SET = 0 Sigma1

56-66 UNRESOLVED RESONANCE REGION TREATMENT Sigma1

= 0 - COPY (NO BROADENING) Sigma1

= 1 - IGNORE (BROADEN) Sigma1

2 1-60 ENDF/B INPUT DATA FILENAME Sigma1

(STANDARD OPTION = ENDFB.IN) Sigma1

3 1-60 ENDF/B OUTPUT DATA FILENAME Sigma1

(STANDARD OPTION = ENDFB.OUT) Sigma1

4-N 1-11 LOWER MAT OR ZA LIMIT Sigma1

12-22 UPPER MAT OR ZA LIMIT Sigma1

UP TO 100 MAT OR ZA RANGES MAY BE SPECIFIED, ONE Sigma1

RANGE PER CARD. THE LIST OF RANGES IS TERMINATED BY Sigma1

A BLANK CARD. IF THE UPPER LIMIT IS LESS THAN THE Sigma1

LOWER LIMIT THE UPPER LIMIT WILL BE SET EQUAL TO THE Sigma1

LOWER LIMIT. IF THE FIRST REQUEST CARD IS BLANK IT Sigma1

WILL TERMINATE THE LIST OF REQUESTS AND CAUSE ALL Sigma1

DATA TO BE RETRIEVED (SEE EXAMPLE INPUT). Sigma1

VARY 1-11 ENERGY FOR ERROR LAW Sigma1

12-22 ERROR FOR ERROR LAW Sigma1

THE ACCEPTABLE LINEARIZING ERROR CAN BE GIVEN AS AN Sigma1

ENERGY DEPENDENT FUNCTION SPECIFIED BY UP TO 20 Sigma1

(ENERGY,ERROR) PAIRS AND LINEAR INTERPOLATION Sigma1

TABULATE POINTS. ENERGIES MUST BE IN ASCENDING ORDER. Sigma1

THE ERROR LAW IS TERMINATED BY A BLANK CARD. IF THE Sigma1

FIRST ERROR LAW CARD IS BLANK IT WILL TERMINATE THE Sigma1

ERROR LAW AND THE ERROR WILL BE TREATED AS ENERGY Sigma1

INDEPENDENT, EQUAL TO ZERO, WHICH INDICATES THAT THE Sigma1

BROADENED DATA SHOULD NOT BE THINNED. Sigma1

Sigma1

EXAMPLE INPUT NO. 1 Sigma1

------------------- Sigma1

BROADEN ALL URANIUM ISOTOPES AND THORIUM-232 TO 300 KELVIN. FROM Sigma1

0 TO 100 EV THIN OUTPUT DATA TO 0.1 PER-CENT ACCURACY. FROM 100 EV Sigma1

TO 1 KEV VARY THE ERROR BETWEEN 0.1 AND 1 PER-CENT. ABOVE 1 KEV Sigma1

USE 1 PER-CENT ACCURACY. Sigma1

Sigma1

EXPLICITLY SPECIFY THE STANDARD FILENAMES. Sigma1

Sigma1

THE FOLLOWING 11 CARDS ARE REQUIRED Sigma1

Sigma1

1 0 3.00000+ 2 Sigma1

ENDFB.IN Sigma1

ENDFB.OUT Sigma1

92000 92999 Sigma1

90232 (UPPER LIMIT WILL AUTOMATICALLY BE DEFINED) Sigma1

(BLANK CARD INDICATES END OF REQUEST LIST) Sigma1

0.00000+ 0 1.00000-03 Sigma1

1.00000+ 2 1.00000-03 Sigma1

1.00000+ 3 1.00000-02 Sigma1

1.00000+ 9 1.00000-02 Sigma1

(BLANK CARD INDICATES END OF ERROR LAW) Sigma1

Sigma1

EXAMPLE INPUT NO. 2 Sigma1

------------------- Sigma1

BROADEN ALL DATA TO 300 KELVIN AND DO NOT THIN THE BROADEN DATA. Sigma1

ALL OF THE STANDARD OPTION MAY BE INVOKED MERELY BY SPECIFYING Sigma1

THE KELVIN TEMPERATURE ON THE FIRST CARD. ALL OTHER FIELDS MAY Sigma1

BE LEFT BLANK. Sigma1

Sigma1

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Sigma1

THEN USE STANDARD FILENAMES. Sigma1

Sigma1

THE FOLLOWING 5 CARDS ARE REQUIRED Sigma1

Sigma1

3.00000+ 2 Sigma1

(USE STANDARD FILENAME = ENDFB.IN) Sigma1

(USE STANDARD FILENAME = ENDFB.OUT) Sigma1

(RETRIEVE ALL DATA, TERMINATE REQUEST LIST) Sigma1

(0.0 ALLOWABLE ERROR, TERMINATE ERROR LAW) Sigma1

Sigma1

EXAMPLE INPUT NO. 3 Sigma1

------------------- Sigma1

THE SAME AS ABOVE, ONLY DEFINE THE MINIMUM CROSS SECTION OF Sigma1

INTEREST TO BE 1.0E-30 BARNS (INSTEAD OF THE DEFAULT VALUE OF Sigma1

1.0E-10). Sigma1

Sigma1

READ ENDF/B DATA FROM \ENDFB6\RECENT\ZA092238 AND WRITE ENDF/B Sigma1

DATA TO \ENDFB\SIGMA1\ZA092238 Sigma1

Sigma1

THE FOLLOWING 5 CARDS ARE REQUIRED Sigma1

Sigma1

3.00000+ 2 1.00000-30 Sigma1

\ENDFB6\RECENT\ZA092238 Sigma1

\ENDFB6\SIGMA1\ZA092238 Sigma1

(RETRIEVE ALL DATA, TERMINATE REQUEST LIST) Sigma1

(0.0 ALLOWABLE ERROR, TERMINATE ERROR LAW) Sigma1

Sigma1

======================================================================= Sigma1

======================================================================= Sixpak

Sixpak

PROGRAM SIXPAK Sixpak

================================================================== Sixpak

VERSION 92-1 (JANUARY 1992) Sixpak

VERSION 92-2 (FEBRUARY 1992)*INCREASED CORE ALLOCATION TO Sixpak

ACCOMMODATE JEF AND EFF EVALUATIONS. Sixpak

VERSION 92-3 (APRIL 1992) *ADDED ADDITIONAL DATA TESTS. Sixpak

VERSION 92-4 (SEPT. 1992) *CORRECTED KALBACH-MANN CALCULATIONS. Sixpak

*FOR PHOTON PRODUCTION OUTPUT MF=12 Sixpak

(MULTIPLICITY), MF=14 (ISOTROPIC Sixpak

ANGULAR DISTRIBUTIONS) AND MF=15 Sixpak

(SPECTRA) - PREVIOUSLY ONLY MF=15. Sixpak

*FIRST ORDER CORRECTIONS TRANSFORMING Sixpak

CENTER-OF-MASS SPECTRA TO LAB SYSTEM Sixpak

FOR OUTPUT IN MF=5 Sixpak

*CORRECTED ISOTROPIC ANGULAR Sixpak

DISTRIBUTION FLAG (LI) Sixpak

VERSION 94-1 (JANUARY 1994) *VARIABLE ENDF/B INPUT DATA FILENAME Sixpak

TO ALLOW ACCESS TO FILE STRUCTURES Sixpak

(WARNING - INPUT PARAMETER FORMAT Sixpak

HAS BEEN CHANGED) Sixpak

*CLOSE ALL FILES BEFORE TERMINATING Sixpak

(SEE, SUBROUTINE ENDIT) Sixpak

*INCREASED MAXIMUM TABLE SIZE FROM Sixpak

2000 TO 6000. Sixpak

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Sixpak

*IMPROVED COMPUTER INDEPENDENCE Sixpak

*ALL DOUBLE PRECISION Sixpak

*ON SCREEN OUTPUT Sixpak

*UNIFORM TREATMENT OF ENDF/B I/O Sixpak

*IMPROVED OUTPUT PRECISION Sixpak

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Sixpak

POINT READ FOR MORE DIGITS Sixpak

*UPDATED TEST FOR ENDF/B FORMAT Sixpak

VERSION BASED ON RECENT FORMAT CHANGE Sixpak

*GENERAL IMPROVEMENTS BASED ON Sixpak

USER FEEDBACK Sixpak

VERSION 99-2 (JUNE 1999) *ASSUME ENDF/B-VI, NOT V, IF MISSING Sixpak

MF=1, MT-451. Sixpak

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Sixpak

USER FEEDBACK Sixpak

VERS. 2002-1 (JANUARY 2002) *CORRECTED ANGULAR DISTRIBUTION (MF=4) Sixpak

OUTPUT TO INSURE USED FIELDS ARE 0 Sixpak

(MAY 2002) *OPTIONAL INPUT PARAMETERS Sixpak

(NOV. 2002) *EXTENDED TO ALLOW CHARGED PARTICLE Sixpak

ANGULAR DISTRIBUTION IN MF=4 - Sixpak

WARNING - STRICTLY SPEAKING THIS IS Sixpak

NOT LEGAL, SINCE MF=4 IS SUPPOSED TO Sixpak

BE USED ONLY FOR NEUTRON ANGULAR Sixpak

DISTRIBUTIONS - BUT WHERE MT MAKES Sixpak

IT OBVIOUS THAT THE OUTGOING PARTICLE Sixpak

IS NOT A NEUTRON HOPEFULLY IT WILL Sixpak

NOT CAUSE A PROBLEM IF MF=4 IS USED Sixpak

FOR CHARGED PARTICLES. Sixpak

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Sixpak

*INCREASED MAXIMUM TABLE SIZE FROM Sixpak

6,000 TO 12,000. Sixpak

*ADDED DUMMY A FOR ELEMENTS Sixpak

*CORRECTED OUTPUT INTERPOLATON LAWS Sixpak

Sixpak

OWNED, MAINTAINED AND DISTRIBUTED BY Sixpak

------------------------------------ Sixpak

THE NUCLEAR DATA SECTION Sixpak

INTERNATIONAL ATOMIC ENERGY AGENCY Sixpak

P.O. BOX 100 Sixpak

A-1400, VIENNA, AUSTRIA Sixpak

EUROPE Sixpak

Sixpak

ORIGINALLY WRITTEN BY Sixpak

------------------------------------ Sixpak

DERMOTT E. CULLEN Sixpak

UNIVERSITY OF CALIFORNIA Sixpak

LAWRENCE LIVERMORE NATIONAL LABORATORY Sixpak

L-159 Sixpak

P.O. BOX 808 Sixpak

LIVERMORE, CA 94550 Sixpak

U.S.A. Sixpak

TELEPHONE 925-423-7359 Sixpak

E. MAIL CULLEN1@LLNL.GOV Sixpak

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Sixpak

Sixpak

COLLABORATION Sixpak

================================================================== Sixpak

DEVELOPED IN COLLABORATION WITH, Sixpak

Sixpak

*THE NATIONAL NUCLEAR DATA CENTER, BROOKHAVEN NATIONAL LAB Sixpak

Sixpak

*THE NUCLEAR DATA SECTION, IAEA, VIENNA, AUSTRIA Sixpak

Sixpak

*CENTRO TECNICO AEROSPACIAL, SAO JOSE DOS CAMPOS, BRAZIL Sixpak

Sixpak

AS A PART OF AN INTERNATIONAL PROJECT ON THE EXCHANGE OF Sixpak

NUCLEAR DATA Sixpak

Sixpak

ACKNOWLEDGEMENT (VERSION 92-1) Sixpak

================================================================== Sixpak

THE AUTHOR THANKS SOL PEARLSTEIN (BROOKHAVEN NATIONAL LAB) FOR Sixpak

SIGNIFICANTLY CONTRIBUTING TOWARD IMPROVING THE ACCURACY AND Sixpak

COMPUTER INDEPENDENCE OF THIS CODE - THANKS, SOL Sixpak

Sixpak

ACKNOWLEDGEMENT (VERSION 92-4) Sixpak

================================================================== Sixpak

THE AUTHOR THANKS BOB MACFARLANE (LOS ALAMOS) FOR SUGGESTING HOW Sixpak

TO PROPERLY OUTPUT THE PHOTON PRODUCTION DATA TO PUT IT INTO Sixpak

EXACTLY THE FORM NEEDED FOR USE IN PROCESSING CODES. Sixpak

Sixpak

THE AUTHOR THANKS CHRIS DEAN (WINFRITH) FOR POINTING OUT ERRORS Sixpak

IN THE EARLIER TREATMENT OF THE KALBACH-MANN FORMALISM AND IN Sixpak

THE DEFINITION OF THE ISOTROPIC ANGULAR DISTRIBUTION FLAG (LI). Sixpak

Sixpak

AUTHORS MESSAGE Sixpak

================================================================== Sixpak

THE COMMENTS BELOW SHOULD BE CONSIDERED THE LATEST DOCUMENTATION Sixpak

INCLUDING ALL RECENT IMPROVEMENTS. PLEASE READ ALL OF THESE Sixpak

COMMENTS BEFORE IMPLEMENTING AND USING THESE CODES. Sixpak

Sixpak

AT THE PRESENT TIME WE ARE ATTEMPTING TO DEVELOP A SET OF COMPUTER Sixpak

INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE Sixpak

OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECT Sixpak

IT WOULD BE APPECIATED IF YOU WOULD NOTIFY THE AUTHOR OF ANY Sixpak

COMPILER DIAGNOSTICS, OPERATING PROBLEMS OR SUGGESTIONS ON HOW TO Sixpak

IMPROVE THIS PROGRAM. HOPEFULLY, IN THIS WAY FUTURE VERSIONS OF Sixpak

THIS PROGRAM WILL BE COMPLETELY COMPATIBLE FOR USE ON YOUR Sixpak

COMPUTER. Sixpak

Sixpak

PURPOSE Sixpak

================================================================== Sixpak

1) CHECK ALL DOUBLE-DIFFERENTIAL DATA (MF=6) Sixpak

Sixpak

2) OUTPUT EQUIVALENT MF = 4, 5, 12, 14 AND 15 DATA. Sixpak

Sixpak

DATA CHECKING Sixpak

================================================================== Sixpak

ALL OF THE ENDF/B-VI MF=6 DATA IS CHECKED - FOR DETAILS SEE BELOW. Sixpak

Sixpak

THE MF=6 DATA IS NOT CORRECTED AND OUTPUT IN THE ENDF/B FORMAT. Sixpak

IT IS MERELY CHECKED. IF ERRORS ARE FOUND IT IS UP TO THE USER Sixpak

TO TAKE CORRECTIVE ACTION ON THE MF=6 DATA. Sixpak

Sixpak

IN CONTRAST WHEN PROBLEMS ARE FOUND IN DATA WHICH WILL BE OUTPUT Sixpak

IN THE ENDF/B FORMAT (MF=4, 5, 12, 14 AND 15), WHENEVER POSSIBLE Sixpak

CORRECTIVE ACTION WILL BE TAKEN. Sixpak

Sixpak

FURTHER CHECKS AND CORRECTIONS Sixpak

================================================================== Sixpak

ONCE THE DATA HAS BEEN OUTPUT IN MF = 4, 5, 12, 14 AND 15 FORMATS Sixpak

FURTHER CORRECTIVE ACTION CAN BE TAKEN AS FOLLOWS, Sixpak

Sixpak

PROGRAM LEGEND Sixpak

============== Sixpak

CAN BE USED TO CORRECT ANGULAR DISTRIBUTIONS WHICH ARE NEGATIVE, Sixpak

TO CONVERT FROM LEGENDRE COEFFICIENTS TO TABULATED ANGULAR Sixpak

DISTRIBUTIONS AND GENERALLY PERFORM MORE EXTENSIVE TESTS OF Sixpak

ALL MF=4 DATA. Sixpak

Sixpak

PROGRAM EVALPLOT Sixpak

================ Sixpak

VERSION 92-1 AND LATER VERSIONS CAN PLOT ALL OF THE MF=4, 5 AND 15 Sixpak

DATA OUTPUT BY THIS CODE. EARLIER VERSIONS CAN PLOT MF=4 AND 5. Sixpak

GRAPHICS IS AN EXCELLENT WAY TO CHECK THIS DATA. Sixpak

Sixpak

PROGRAM PLOTTAB Sixpak

=============== Sixpak

THIS IS A GENERAL PLOTTING PROGRAM AND THERE IS AN INTERFACE IN Sixpak

THIS CODE TO PRODUCE OUTPUT FOR ANY MF=6 DATA IN THE PLOTTAB Sixpak

INPUT FORMAT. THIS PROGRAM CAN BE USED TO CHECK ALL OF THE MF=6 Sixpak

DATA AS WELL AS THE EQUIVALENT MF=4, 5, 12, 14 AND 15 DATA - AS Sixpak

WELL AS COMPARING THE ORIGINAL MF=6 AND EQUIVALENT DATA. Sixpak

Sixpak

DATA OUTPUT Sixpak

================================================================== Sixpak

THE ENDF/B MF=4, 5, 12, 14 AND 15 FORMATS ONLY ALLOW FOR NEUTRONS Sixpak

INCIDENTS Sixpak

Sixpak

THE ENDF/B MF=4 AND 5 FORMATS ONLY ALLOW FOR NEUTRONS OUTGOING. Sixpak

Sixpak

THE ENDF/B MF=12, 14 AND 15 ONLY ALLOWS FOR PHOTONS OUTGOING. Sixpak

Sixpak

THESE ARE THE ONLY COMBINATIONS OF DATA OUTPUT BY THIS CODE. Sixpak

Sixpak

ALL OTHER COMBINATIONS OF INCIDENT AND OUTGOING PARTICLES ARE Sixpak

CHECKED, BUT THE RESULTS CANNOT BE OUTPUT IN THE ENDF/B FORMAT. Sixpak

HOWEVER, USING THE PLOTTAB INTERFACE BUILT INTO THIS CODE THIS Sixpak

DATA CAN, AND HAS BEEN, OUTPUT AND CHECKED. Sixpak

Sixpak

THE NEUTRON DATA IN MF=4 CAN BE IN THE FORM OF EITHER TABULATED Sixpak

ANGULAR DISTRIBUTIONS OR LEGENDRE COEFFICIENTS. Sixpak

Sixpak

THE NEUTRON (MF=5) OR PHOTON (MF=15) SPECTRA ARE BOTH IN EXACTLY Sixpak

THE SAME FORMAT = ARBITRARY TABULATED FUNCTIONS - ENDF/B OPTION Sixpak

LF=1. Sixpak

Sixpak

ENDF/B DATA OUTPUT ORDER Sixpak

================================================================== Sixpak

ENDF/B DATA IS OUTPUT IN ASCENDING MAT, MF, MT ORDER. IN ORDER TO Sixpak

ALLOW THIS PROGRAM TO PRODUCE ALL OUTPUT IN A SINGLE PASS THROUGH Sixpak

THE MF=6 DATA, OUTPUT FOR EACH (MAT, MT) IS OUTPUT TO SEPERATE Sixpak

FILES FOR MF=4, 5, 12, 14 AND 15. Sixpak

Sixpak

FOR SUBSEQUENT USE THE ENDF/B FORMATTED DATA OUTPUT BY THIS CODE Sixpak

CAN BE MERGED TOGETHER USING PROGRAM MERGER (CONTAIN THE AUTHOR Sixpak

OF THIS CODE FOR A COPY OF MERGER), E.G., MERGE MF=12, 14 AND 15 Sixpak

DATA IN ORDER TO THEN CALCULATE PHOTON PRODUCTION DATA OR MF=4 Sixpak

AND 5 CAN BE MERGED TOGETHER TO CALCULATE NEUTRON TRANSFER - OR Sixpak

ALL OF THEM CAN BE MERGED TOGETHER TO PERFORM NEUTRON AND PHOTON Sixpak

CALCULATIONS. Sixpak

Sixpak

CORRELATED (MF=6) VS. UNCORRELATED (MF=4 AND 5) DATA Sixpak

================================================================== Sixpak

THE ENDF/B DOUBLE DIFFERENTAL = CORRELATED - DATA IN MF=6 Sixpak

REPRESENTS DATA IN THE FORM, Sixpak

Sixpak

F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS) Sixpak

Sixpak

SIG(E) = MF=3 CROSS SECTIONS Sixpak

Y(E) = YIELD (MULTIPLICITY) Sixpak

G0(E,EP) = ENERGY SPECTRUM Sixpak

F(E,EP,COS) = ANGULAR DISTRIBUTION Sixpak

Sixpak

IN A SITUATION WHERE YOU HAVE MONOENERGETIC AND MONODIRECTIONAL Sixpak

NEUTRONS INCIDENT YOU WILL BE ABLE TO OBSERVE CORRELATION EFFECTS Sixpak

IN THE NEUTRON SPECTRUM AND ANGULAR DISTRIBUTION. Sixpak

Sixpak

EVEN IN SITUATIONS WHERE YOU HAVE A NARROW SPECTRUM OF NEUTRONS Sixpak

THAT ARE HIGHLY DIRECTIONALLY ORIENTED YOU MAY BE ABLE TO OBSERVE Sixpak

THESE CORRELATION EFFECTS, E.G., A NARROW 14 MEV FUSION SOURCE Sixpak

INCIDENT ON THE FIRST WALL OF A CTR DEVICE. Sixpak

Sixpak

FOR SUCH SITUATIONS USE OF THE CORRELATED (MF=6) DATA IS REQUIRED Sixpak

IN CALCULATIONS. Sixpak

Sixpak

HOWEVER, IN MANY APPLICATIONS WHERE THERE IS A BROAD SPECTRUM OF Sixpak

NEUTRONS AND THE NEUTRON FLUX IS NOT HIGHLY DIRECTIONALLY Sixpak

ORIENTED, THE NEUTRON MULTIPLICATION, SPECTRUM AND ORIENTATION Sixpak

CAN BE FAIRLY ACCURATELY CALCULATED WITHOUT CONSIDERING Sixpak

CORRELATION EFFECTS. Sixpak

Sixpak

THE UNCORRELATED DATA PRODUCED BY THIS CODE REPLACES THE Sixpak

CORRELATED DATA, Sixpak

Sixpak

F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS) Sixpak

Sixpak

BY THE UNCORRELATED DATA, Sixpak

Sixpak

F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F0(E,COS) Sixpak

Sixpak

BY INTEGRATING G0(E,EP)*F(E,EP,COS) OVER SECONDARY ENERGY (EP) Sixpak

TO DEFINE AN AVERAGE ANGULAR DISTRIBUTION, F0(E,COS). Sixpak

Sixpak

WHAT IS LOST IN THIS PROCESS IS THE CORRELATION BETWEEN EP AND COS Sixpak

SO THAT IN A TRANSPORT CALCULATION ALL MOMENTS OF THE FLUX WILL Sixpak

HAVE THE SAME SPECTRUM, G0(E,EP) AND EACH WILL BE EFFECTED BY THE Sixpak

AVERAGE ANGULAR DISTRIBUTION. Sixpak

Sixpak

FOR APPLICATIONS TO HIGH ENERGY FUSION APPLICATIONS CORRELATED Sixpak

DATA SHOULD BE USED. HOWEVER, FOR LOWER ENERGY APPLICATIONS, Sixpak

SUCH AS FISSION REACTORS, IT SHOULD BE ADEQUATE TO USE THE Sixpak

UNCORRELATED DATA - IN THIS CASE THE MOST IMPORTANT EFFECT Sixpak

WILL BE THE OVERALL NEUTRON MULTIPLICATION AND SPECTRUM. Sixpak

Sixpak

AN IMPORTANT CONSIDERATION IN DESIGNING THIS PROGRAM IS THAT Sixpak

MANY COMPUTER CODES - DATA PROCESSING AND TRANSPORT CODES - Sixpak

CANNOT USE THE CORRELATED (MF=6) DATA - NOR ARE THEY INTENDED Sixpak

FOR HIGH ENERGY USE. FOR THESE CODES THE UNCORRELATED DATA Sixpak

PRODUCED BY THIS CODE SHOULD BE ADEQUATE TO MEET THEIR NEEDS. Sixpak

Sixpak

WARNING - IT CANNOT BE STRESSED ENOUGH THAT THE OUTPUT OF THIS Sixpak

CODE SHOULD ONLY BE USED FOR LOW ENERGY APPLICATIONS - FAILURE Sixpak

TO HEED THIS WARNING CAN LEAD TO COMPLETELY UNRELIABLE RESULTS. Sixpak

Sixpak

ENDF/B FORMAT Sixpak

================================================================== Sixpak

THIS PROGRAM ONLY USES THE ENDF/B BCD OR CARD IMAGE FORMAT (AS Sixpak

OPPOSED TO THE BINARY FORMAT) AND CAN HANDLE DATA IN ANY VERSION Sixpak

OF THE ENDF/B FORMAT (I.E., ENDF/B-I, II,III, IV, V OR VI FORMAT). Sixpak

Sixpak

IT IS ASSUMED THAT THE DATA IS CORRECTLY CODED IN THE ENDF/B Sixpak

FORMAT AND NO ERROR CHECKING IS PERFORMED. IN PARTICULAR IT IS Sixpak

ASSUMED THAT THE MAT, MF AND MT ON EACH LINE IS CORRECT. SEQUENCE Sixpak

NUMBERS (COLUMNS 76-80) ARE IGNORED ON INPUT, BUT WILL BE Sixpak

CORRECTLY OUTPUT ON ALL LINES. THE FORMAT OF SECTION MF=1, MT=451 Sixpak

AND ALL SECTIONS OF MF=6 MUST BE CORRECT. THE PROGRAM SKIPS ALL Sixpak

OTHER SECTIONS OF DATA AND AS SUCH IS INSENSITIVE TO THE FORMAT Sixpak

OF ALL OTHER SECTIONS. Sixpak

Sixpak

CONTENTS OF OUTPUT Sixpak

================================================================== Sixpak

5 ENDF/B FORMATTED OUTPUT FILES ARE PRODUCED FOR NEUTRON INCIDENT Sixpak

DATA, Sixpak

Sixpak

1) ENDFB.MF4 - ANGULAR DISTRIBUTIONS AND LEGENDRE COEFFICIENTS Sixpak

FOR NEUTRONS Sixpak

2) ENDFB.MF5 - TABULATED NEUTRON ENERGY SPECTRA Sixpak

3) ENDFB.M12 - PHOTON EMISSION MULTIPLICITY Sixpak

4) ENDFB.M14 - PHOTON EMISSION ANGULAR DISTRIBUTIONS (ALWAYS Sixpak

ISOTROPIC) Sixpak

5) ENDFB.M15 - TABULATED PHOTON EMISSION SPECTRA Sixpak

Sixpak

EMITTED PARTICLE YIELD Sixpak

================================================================== Sixpak

NEUTRONS Sixpak

======== Sixpak

IN MF=6 THE YIELD FOR EACH REACTION IS THE ACTUAL MULTIPLICITY OF Sixpak

THE REACTION, E.G., (N,2N) = 2. IN USING MF=4 AND 5 DATA THE Sixpak

ENDF/B CONVENTION IS THAT THE MULTIPLICITY IS IMPLIED BY THE Sixpak

MT NUMBER, E.G., MT=16 = (N,2N) = 2. Sixpak

Sixpak

THE ONLY EXCEPT IN ENDF/B-VI IS MT=201 = TOTAL NEUTRON PRODUCTION Sixpak

WHERE AN ACTUAL ENERGY DEPENDENT YIELD IS INCLUDED IN MF=6. Sixpak

HOWEVER, IN THIS CASE THE MF=3 CROSS SECTION INCLUDES THE Sixpak

MULTIPLICITY (S. PEARLSTEIN, PRIVATE COMMUNICATION, JAN. 1992), Sixpak

SIG(MT=201) = 2*SIG(N,2N)+3*SIG(N,3N).....ETC. Sixpak

Sixpak

SO THAT FOR ALL ENDF/B-VI DATA AS OF JANUARY 1992 THE MF=4 AND 5 Sixpak

DATA OUTPUT BY THIS CODE CAN BE USED IN CONJUNCTION WITH THE MF=3 Sixpak

CROSS SECTIONS - WITHOUT ANY REFERENCE TO THE MF=6 YIELD. Sixpak

Sixpak

PHOTONS Sixpak

======= Sixpak

UNLIKE THE NEUTRONS WHERE WITH ONLY ONE EXCEPTION (MT=201) THE Sixpak

MF=6 YIELD IS ENERGY INDEPENDENT, IN THE CASE OF PHOTON EMISSION Sixpak

ALMOST ALL OF THE PHOTONS HAVE AN ENERGY DEPENDENT YIELD. Sixpak

Sixpak

THIS PROGRAM WILL OUTPUT THE PHOTON MULTIPLICITY IN MF=12 AND Sixpak

INDICATE THAT THERE IS A NORMALIZED DISTRIBUTION IN MF=15 Sixpak

(LF=1 IN MF=12). Sixpak

Sixpak

THIS PROGRAM WILL OUTPUT THE NORMALIZED PHOTON SPECTRA IN MF=15. Sixpak

CONTINUOUS ENERGY SPECTRA AND DISCRETE PHOTONS WILL ALL BE OUTPUT Sixpak

AS NORMALIZED SPECTRA. Sixpak

Sixpak

THIS PROGRAM WILL ALSO OUTPUT MF=14 PHOTON ANGULAR DISTRIBUTION Sixpak

DATA, ALWAYS USING THE ISOTROPIC FLAG TO MINIMIZE OUTPUT. Sixpak

Sixpak

WARNING OF ENERGY DEPENDENT YIELD Sixpak

================================= Sixpak

THIS PROGRAM WILL PRINT A WARNING MESSAGE IF A SECTION OF DATA Sixpak

BEING OUTPUT IN THE ENDF/B FORMAT HAS AN ENERGY DEPENDENT MF=6 Sixpak

YIELD AND THE EMITTED PARTICLE IS A NEUTRON - SINCE THE ENDF/B Sixpak

CONVENTION IS THAT FOR EACH MT NUMBER THE MULTIPLICITY IS IMPLIED Sixpak

WE DO NOT EXPECT AN ENERGY DEPENDENT MULTIPLICITY FOR NEUTRON Sixpak

EMISSION. Sixpak

Sixpak

USING THE OUTPUT Sixpak

================================================================== Sixpak

NOTE, THAT IN USING THIS DATA, STARTING FROM THE RELATIONSHIP, Sixpak

Sixpak

F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F0(E,COS) Sixpak

Sixpak

USING THE ENDF/B CONVENTION THAT THE MULTIPLICITY IS EITHER Sixpak

IMPLIED BY THE MT NUMBER (E.G., MT=16 = N,2N - MULTIPLICITY = 2) Sixpak

OR INCLUDED IN THE CROSS SECTION (E.G., MT=201 = TOTAL NEUTRON Sixpak

PRODUCTION) ALL THE INFORMATION REQUIRED FOR A CALCULATION IS Sixpak

AVAILABLE IN, Sixpak

Sixpak

MF=3 - SIG(E) Sixpak

MF=4 - F0(E,COS) - FOR OUTGOING NEUTRONS Sixpak

MF=5 - G0(E,EP) - FOR OUTGOING NEUTRONS Sixpak

MF=12 - Y(E) - FOR OUTGOING PHOTONS Sixpak

MF=14 - F0(E,COS) - FOR OUTGOING PHOTONS (ALWAYS ISOTROPIC) Sixpak

MF=15 - G0(E,EP) - FOR OUTGOING PHOTONS Sixpak

Sixpak

DOCUMENTATION Sixpak

================================================================== Sixpak

ONLY SECTIONS OF MF=4, 5, 12, 14, 15 ARE OUTPUT ON A ENDF/B FILE. Sixpak

THE ONLY DOCUMENTATION IS THE ENDF/B TAPE LABEL (FIRST RECORD OF Sixpak

EACH FILE) WHICH IDENTIFIES THE DATA AS SIXPAK OUTPUT. Sixpak

Sixpak

REACTION INDEX Sixpak

================================================================== Sixpak

THIS PROGRAM DOES NOT USE THE REACTION INDEX WHICH IS GIVEN IN Sixpak

SECTION MF=1, MT=451 OF EACH EVALUATION. Sixpak

Sixpak

SECTION SIZE Sixpak

================================================================== Sixpak

ALL OF THE DATA IN ENDF/B-VI, MF=6 ARE QUITE SMALL TABLES. AS SUCH Sixpak

THIS PROGRAM ONLY ALLOWS TABLES OF UP TO 12000 POINTS (12,000 X, Sixpak

Y VALUES). THIS SIZE IS MORE THAN ADEQUATE TO HANDLE ALL OF THE Sixpak

CURRENT ENDF/B-VI DATA, AND IT CAN BE EASILY INCREASED TO HANDLE Sixpak

ANY NEWER DATA AS IT BECOMES AVAILABLE. Sixpak

Sixpak

PLEASE CONTACT THE AUTHOR IF YOU HAVE AN EVALUATION WHICH EXCEEDS Sixpak

THIS LIMIT. Sixpak

Sixpak

SELECTION OF DATA Sixpak

================================================================== Sixpak

THE PROGRAM SELECTS DATA TO BE PROCESSED BASED ON MAT/MT RANGES Sixpak

(MF=6 ASSUMED). THIS PROGRAM ALLOWS UP TO 100 MAT/MT RANGES TO BE Sixpak

SPECIFIED BY INPUT PARAMETERS. THE PROGRAM WILL ASSUME THAT THE Sixpak

ENDF/B TAPE IS IN MAT ORDER. THE PROGRAM WILL TERMINATE EXECUTION Sixpak

WHEN A MAT IS FOUND THAT IS ABOVE ALL REQUESTED MAT RANGES. Sixpak

Sixpak

PROGRAM OPERATION Sixpak

================================================================== Sixpak

EACH SECTION (MT) OF MF=6 DATA IS SUBDIVIDED INTO SUBSECTIONS - Sixpak

ONE SUBSECTION FOR EACH EMITTED PARTICLE. Sixpak

Sixpak

EACH SUBSECTION OF DATA IS CONSIDERED SEPARATELY. EACH SUBSECTION Sixpak

OF ENDF/B MF=6 DATA TO PROCESS IS IN THE FORM, Sixpak

Sixpak

F(E,EP,COS) = SIG(E)*Y(E)*G0(E,EP)*F(E,EP,COS) Sixpak

Sixpak

SIG(E) = MF=3 CROSS SECTIONS Sixpak

Y(E) = YIELD (MULTIPLICITY) Sixpak

G0(E,EP) = ENERGY SPECTRUM Sixpak

F(E,EP,COS) = ANGULAR DISTRIBUTION Sixpak

Sixpak

G0(E,EP) = 1 WHEN INTEGRATED OVER EP (SECONDARY ENERGY) Sixpak

G0(E,EP)*F(E,EP,COS) = 1 WHEN INTEGRATED OVER EP AND COS Sixpak

Sixpak

THIS PROGRAM WILL DEFINE THE ZEROTH ORDER MOMENTS OF THE Sixpak

ENERGY AND ANGULAR DISTRIBUTIONS, Sixpak

Sixpak

G0(E,EP) = G0(E,EP)*F(E,EP,COS) INTEGRATED OVER COS Sixpak

F0(E,COS) = G0(E,EP)*F(E,EP,COS) INTEGRATED OVER EP Sixpak

Sixpak

FOR NEUTRON INDUCED REACTIONS THE ENDF/B FORMATTED OUTPUT WILL BE Sixpak

Sixpak

F0(E,COS)- IN ENDFB.MF4 FOR NEUTRONS OUT OF A REACTION Sixpak

G0(E,EP) - IN ENDFB.MF5 FOR NEUTRONS OUT OF A REACTION Sixpak

- IN ENDFB.M15 FOR PHOTONS OUT OF A REACTION Sixpak

Sixpak

FOR NEUTRONS INCIDENT AND NEUTRONS EMITTED THIS DATA WILL BE Sixpak

OUTPUT IN MF=4 AND 5 FORMATS. Sixpak

Sixpak

FOR NEUTRONS INCIDENT AND PHOTONS EMITTED THIS DATA WILL BE Sixpak

OUTPUT IN MF=15 FORMAT - THE SPECTRA ARE OUTPUT AND THE Sixpak

ANGULAR DISTRIBUTION IS IGNORED. Sixpak

Sixpak

ALL PHOTON EMISSION IN THE ENDF/B-VI LIBRARY AS OF JANUARY 1992 Sixpak

IS ISOTROPIC AND AS SUCH NO DISTRIBUTION OF PHOTON ANGULAR Sixpak

DISTRIBUTIONS NEED BE OUTPUT - IT IS ALWAYS ISOTROPIC. Sixpak

Sixpak

FOR ALL OTHER COMBINATIONS INCIDENT AND EMITTED PARTICLES Sixpak

THERE WILL BE NO ENDF/B FORMATTED OUTPUT. Sixpak

Sixpak

VARIATIONS FROM ENDF/B MANUAL Sixpak

================================================================== Sixpak

LAW=1, LANG=2 = KALBACH-MANN Sixpak

============================ Sixpak

FOR THE DISTRIBUTIONS, Sixpak

Sixpak

F(MU,E,EP) = G0(E,EP)*A*(COSH(MU*A)+R(E,EP)*SINH(MU*A)) Sixpak

Sixpak

G0(E,EP) = 1 - WHEN INTEGRATED OVER EP. Sixpak

Sixpak

A*(COSH(MU*A)+R(E,EP)*SINH(MU*A)) = 2 - WHEN INTEGRATD OVER MU Sixpak

Sixpak

THIS MEANS AS DEFINED IN THE ENDF/B MANUAL THE DISTRIBUTIONS Sixpak

ARE NORMALIZED TO 2, INSTEAD OF 1. IN ORDER TO OBTAIN CORRECTLY Sixpak

NORMALIZED DISTRIBUTIONS THE DISTRIBUTION SHOULD BE DEFINED Sixpak

TO INCLUDE A FACTOR OF 1/2 MULTIPLYING THE ANGULAR PART OF Sixpak

THE DISTRIBUTION. Sixpak

Sixpak

F(MU,E,EP) = G0(E,EP)*0.5*A*(COSH(MU*A)+R(E,EP)*SINH(MU*A)) Sixpak

Sixpak

THIS IS THE FORM USED IN THIS CODE Sixpak

Sixpak

LAW=1, ND NOT 0 = DISCRETE SECONDARY ENERGY DISTRIBUTION Sixpak

======================================================== Sixpak

THE ENDF/B MANUAL SAYS THESE ARE FLAGGED WITH NEGATIVE ENERGIES. Sixpak

IN ENDF/B-VI ALL OF THESE HAVE POSITIVE ENERGY. THIS CODE DOES Sixpak

NOT CONSIDER THE ENDF/B-VI DATA TO BE IN ERROR. Sixpak

Sixpak

WITH THE CONVENTION ACTUALLY USED IN ENDF/B-VI ALL SECONDARY Sixpak

ENERGIES SHOULD BE NON-NEGATIVE AND IN ASCENDING ENERGY ORDER Sixpak

FOR EACH INCIDENT ENERGY. Sixpak

Sixpak

FROM THE ENDF/B MANUAL IT IS NOT OBVIOUS WHAT G0(E,EP) SHOULD BE Sixpak

FOR DISCRETE PHOTONS - PHYSICALLY THIS IS A DELTA FUNCTION. IN Sixpak

ENDF/B-VI IT IS ENTERED AS 1.0 = INTERPRETING IT AS INTEGRATED Sixpak

OVER SECONDARY ENERGY - IN WHICH CASE THE DELTA FUNCTION = 1.0. Sixpak

Sixpak

LIMITATIONS Sixpak

================================================================== Sixpak

CHECKING DATA Sixpak

================================================================== Sixpak

THIS PROGRAM CHECKS ALL ENDF/B-VI MF=6 DATA. THE FOLLOWING CHECKS Sixpak

ARE PERFORMED. Sixpak

Sixpak

PARAMETERS Sixpak

========== Sixpak

ALL PARAMETERS ARE CHECKED FOR CONSISTENCY. IF PARAMETERS ARE Sixpak

NOT CONSISTENT THE PROGRAM MAY NOT BE ABLE TO PERFORM THE Sixpak

FOLLOWING TESTS AND WILL MERELY SKIP A SECTION OF DATA. Sixpak

Sixpak

INTERPOLATION LAWS Sixpak

================== Sixpak

ALL INTEGRATIONS ARE PERFORMED USING THE INTERPOLATION LAW GIVEN Sixpak

FOR SECONDARY ENERGY AND/OR COSINE. INTEGRATIONS ARE NOT Sixpak

PERFORMED OVER INCIDENT - ONLY INTEGRATION OVER SECONDARY ENERGY Sixpak

AND/OR COSINE ARE PERFORMED AT EACH INCIDENT ENERGY. THEREFORE Sixpak

THE INTERPOLATION LAW FOR INCIDENT ENERGY IS NOT USED BY THIS Sixpak

CODE. Sixpak

Sixpak

ALL INTERPOLATION LAWS ARE CHECKED. ALL DATA ASSOCIATED WITH Sixpak

INTERPOLATION LAWS ARE CHECKED, E.G., NO NON-NEGATIVE VALUES Sixpak

REQUIRING LOG INTERPOLATION. IN ORDER TO PERFORM REQUIRED Sixpak

INTEGRALS OVER COS AND EP IT IS IMPERATIVE THAT THE INTERPOLATION Sixpak

LAWS BE COMPATIBLE WITH THE DATA. Sixpak

Sixpak

ENDF/B-VI ALLOWS NEW INTERPOLATION LAWS FOR CORRESPONDING POINT Sixpak

AND UNIT BASE TRANSFORMATION INTERPOLATION. NONE OF THESE NEW Sixpak

INTERPOLATION LAWS ARE USED IN THE ENDF/B-VI LIBRARY AS OF Sixpak

JANUARY 1992 TO INTERPOLATE IN SECONDARY ENERGY OR COSINE. Sixpak

THEREFORE THIS PROGRAM CAN PERFORM ALL OF THE REQUIRED INTEGRALS Sixpak

OVER SECONDARY ENERGY AND/OR COSINE USING ONLY THE OLDER Sixpak

INTERPOLATION CODES. THIS PROGRAM ONLY PERFORMS INTEGRALS FOR Sixpak

EACH INCIDENT ENERGY, SO THAT INTERPOLATION IN INCIDENT ENERGY Sixpak

IS NOT PERFORMED BY THIS PROGRAM. Sixpak

Sixpak

NEW INTERPOLATION SCHEMES ARE USED FOR INCIDENT ENERGY - FOR Sixpak

EXAMPLE, CORRESPONDING POINT INTERPOLATION IS SPECIFIED TO ALLOW Sixpak

INTERPOLATION IN G0(E,EP) TO SIMULATE CASES WHERE THE INPUT ENERGY Sixpak

LIMIT IS DEFINED BY E-EP = A DIAGONAL CURVE ACROSS (E,EP) SPACE. Sixpak

THIS INTERPOLATION CODE CANNOT BE SPECIFIED IN THE MF=5 OUTPUT Sixpak

OF THIS CODE - MF=5 ONLY ALLOWS THE OLDER INTERPOLATION LAWS Sixpak

INT=1 THROUGH 5. THEREFORE THIS PROGRAM WILL USE THE CLOSEST Sixpak

CORRESPONDING INTERPOLATION CODE FOR OUTPUT TO MF=5. FOR USE Sixpak

WHERE THE OUTPUT OF THIS CODE = LOW ENERGY APPLICATIONS - THIS Sixpak

SHOULD HAVE LITTLE EFFECT ON RESULTS. Sixpak

Sixpak

FOR CONSISTENCY WITH EARLIER VERSIONS OF ENDF/B IN CREATING THE Sixpak

ENDF/B OUTPUT, IF ANY INPUT INTERPOLATION LAW IS NOT IN THE Sixpak

RANGE 1-5, IT WILL FIRST BE TESTED TO SEE IF MOD(10) IT IS Sixpak

IN THIS RANGE, FINALLY IF EVEN THIS DOESN'T WORK IT IS SET Sixpak

EQUAL TO 2 (LINEARLY INTERPOLATION). THIS METHOD WILL EFFECTIVELY Sixpak

REPLACE CORRESPONDING POINT AND UNIT BASE TRANSFORMATION BY THE Sixpak

CLOSEST RELATED INTERPOLATION LAW 1 THROUGH 5 - AGAIN NOTE, AS Sixpak

OF JANUARY 1992 NONE OF THESE NEW LAWS ARE USED IN ENDF/B-VI. IF Sixpak

THIS MUST BE DONE FOR INTERPOLATION IN SECONDARY ENERGY OR COSINE Sixpak

AN ERROR MESSAGE WILL BE PRINTED - SINCE THIS WOULD EFFECT THE Sixpak

ACCURACY OF THE INTEGRALS PERFORMED BY THIS PROGRAM. IF THIS MUST Sixpak

BE DONE FOR INCIDENT ENERGY NO MESSAGE IS PRINTED - SINCE THIS Sixpak

WILL NOT EFFECT THE ACCURACY OF THE INTEGRALS PERFORMED BY THIS Sixpak

PROGRAM. Sixpak

Sixpak

SPECTRA AND ANGULAR DISTRIBUTIONS Sixpak

================================= Sixpak

ALL SPECTRA AND ANGULAR DISTRIBUTIONS ARE CHECKED TO INSURE Sixpak

THEY ARE NORMALIZED AND DO NOT INCLUDE ANY NEGATIVE VALUES. Sixpak

Sixpak

LEGENDRE COEFFICIENTS Sixpak

===================== Sixpak

THE NORMALIZATION, F0, CANNOT BE NEGATIVE. Sixpak

Sixpak

LEGENDRE COEFFICIENTS IN NORMAL FORM ARE CHECKED TO INSURE Sixpak

THEY ARE IN THE RANGE -1 TO +1 = THE LEGENDRE EXPANSION OF A Sixpak

DELTA FUNCTION AT COS=+1 OR -1 - COEFFICIENTS SHOULD NOT Sixpak

EXCEED WHAT YOU GET FROM A DELTA FUNCTION. Sixpak

Sixpak

ANGULAR DISTRIBUTIONS ARE CHECKED AT COS = -1, 0 AND +1. Sixpak

Sixpak

CREATING ENDF/B OUTPUT Sixpak

================================================================== Sixpak

THIS PROGRAM CAN CREATE EQUIVALENT MF =4, 5, 12, 14, 15 DATA FOR Sixpak

ALL OF THE DATA INCLUDED IN ENDF/B-VI AS OF JANUARY 1992, EXCEPT Sixpak

FOR 1 SECTION OF LAW=6 DATA (SEE DETAILS BELOW). Sixpak

Sixpak

THIS PROGRAM HAS NOT BEEN TESTED ON OTHER DATA LIBRARIES, E.G., Sixpak

JEF, JENDL, ETC. Sixpak

Sixpak

THE PROGRAM HAS THE FOLLOWING LIMITATION AS FAR AS CREATING Sixpak

ENDF/B FORMATTED OUTPUT. Sixpak

Sixpak

ISOTROPIC PHOTON EMISSION Sixpak

========================= Sixpak

FOR PHOTON EMISSION THE DISTRIBUTIONS ARE ASSUMED TO BE ISOTROPIC Sixpak

AND ONLY THE MULTIPLICITY IS OUTPUT IN MF=12, ISOTROPIC ANGULAR Sixpak

DISTRIBUTIONS IN MF=14 AND THE SPECTRA IN MF=15. ALL ENDF/B-VI Sixpak

MF=6 DATA AS OF JANUARY 1992 INCLUDE ONLY ISOTROPIC PHOTON Sixpak

EMISSION - SO THAT THIS IS NOT A LIMITATION ON TRANSLATING Sixpak

ENDF/B-VI DATA. Sixpak

Sixpak

EITHER TABULATED OR LEGENDRE COEFFICIENTS Sixpak

========================================= Sixpak

FOR LAW=2 THE REPRESENTATION, EITHER TABULATED OR LEGENDRE Sixpak

COEFFICIENTS, CAN BE SPECIFIED FOR EACH INCIDENT ENERGY. Sixpak

Sixpak

IN ORDER TO OBTAIN CORRECT ENDF/B OUTPUT THE REPRESENTATION Sixpak

MUST BE THE SAME FOR ALL INCIDENT ENERGIES = MF=4 DATA CAN ONLY Sixpak

BE TABULATED OR LEGENDRE OVER THE ENTIRE ENERGY RANGE. Sixpak

Sixpak

YIELD AND OUTPUT NORMALIZATION Sixpak

============================== Sixpak

THE YIELD INCLUDED WITH EACH SECTION OF DATA IS NOT USED FOR Sixpak

OUTPUT FOR NEUTRONS, BUT IS INCLUDED IN THE OUTPUT FOR PHOTONS. Sixpak

IN ALL CASES THE ANGULAR DISTRIBUTIONS AND SPECTRA OUTPUT ARE Sixpak

NORMALIZED TO UNITY. Sixpak

Sixpak

LAW=0 Sixpak

===== Sixpak

NO OUTPUT - INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON Sixpak

REACTIONS ARE NOT EXPECTED. Sixpak

Sixpak

LAW=1 Sixpak

===== Sixpak

FOR EACH INCIDENT ENERGY DISCRETE AND CONTINUOUS EMISSION SPECTRA Sixpak

CANNOT BE MIXED TOGETHER - THEY MUST BE ALL EITHER DISCRETE OR Sixpak

CONTINUOUS. IF DISCRETE EMISSION IS GIVEN ONLY 1 SECONDARY Sixpak

ENERGY (NEP=1) MAY BE GIVEN = A NORMALIZED DISTRIBUTION FOR A Sixpak

SINGLE DISCRETE EMISSION ENERGY. ALL OF THE ENDF/B-VI DATA AS Sixpak

OF JANUARY 1992 CONFORM TO THESE LIMITATIONS. Sixpak

Sixpak

SINCE THE FLAG NA, TO INDICATE ISOTROPIC DISTRIBUTIONS, IS ONLY Sixpak

GIVEN FOR EACH SECONDARY ENERGY (EP) THE PROGRAM CANNOT DECIDE Sixpak

IN ADVANCE WHETHER OR NOT THE DISTRIBUTION WILL BE ISOTROPIC Sixpak

AT ALL INCIDENT ENERGIES. THEREFORE ISOTROPIC DISTRIBUTIONS Sixpak

WILL BE OUTPUT EITHER: LANG = 1 - AS 1 LEGENDRE COEFFICIENT = 0.0 Sixpak

OR LANG = NOT 1 - AS A 2 POINT ANGULAR DISTRIBUTION AT COS = -1.0 Sixpak

AND +1.0 WITH BOTH VALUES EQUAL TO 0.5 (A NORMALIZED ISOTROPIC Sixpak

DISTRIBUTION). Sixpak

Sixpak

DISCRETE PHOTONS ARE OUTPUT IN MF=15 AS 3 POINT DISTRIBUTIONS Sixpak

WITH SECONDARY ENERGY POINTS AT EP-DEP, EP, EP+DEP, WHERE Sixpak

DEP=0.001*EP. THE VALUES AT EP-DEP AND EP+DEP ARE 0.0, AND Sixpak

AT EP THE VALUE IS 1000.0/EP TO NORMALIZE THE DISTRIBUTION. Sixpak

Sixpak

LAW=2 Sixpak

===== Sixpak

NO LIMITATION ON REPRESENTATIONS. Sixpak

Sixpak

LAW=3 Sixpak

===== Sixpak

NO LIMITATION ON REPRESENTATIONS. Sixpak

Sixpak

LAW=4 Sixpak

===== Sixpak

NO OUTPUT - INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON Sixpak

REACTIONS ARE NOT EXPECTED. Sixpak

Sixpak

LAW=5 Sixpak

===== Sixpak

NO OUTPUT - INCIDENT NEUTRON - EMITTED PHOTON OR NEUTRON Sixpak

REACTIONS ARE NOT EXPECTED. Sixpak

Sixpak

LAW=6 Sixpak

===== Sixpak

NO OUTPUT - ENDF/B-VI ONLY INCLUDES 1 SECTION OF THIS TYPE OF DATA Sixpak

FOR (N,D) 2N,P. Sixpak

Sixpak

LAW=7 Sixpak

===== Sixpak

FOR EACH INCIDENT ENERGY THE REPRESENTATION MUST BE EITHER, Sixpak

Sixpak

1) SQUARE = FOR EACH INCIDENT COSINE EXACTLY THE SAME SECONDARY Sixpak

ENERGIES. Sixpak

Sixpak

2) LINEAR = FOR EACH INCIDENT COSINE THE INTERPOLATION LAW Sixpak

BETWEEN SECONDARY ENERGIES MUST BE LINEAR. Sixpak

Sixpak

THESE 2 PRESENTATIONS ARE THE ONLY ONES PRESENTED IN ENDF/B-VI Sixpak

AS OF JANUARY 1992 - SO THIS PROGRAM CAN TRANSLATED ALL LAW=7 Sixpak

DATA FOR ENDF/B-VI. Sixpak

Sixpak

LABORATORY VS. CENTER-OF-MASS SYSTEM Sixpak

================================================================== Sixpak

IN MANY CASES PEOPLE ASSUME THAT FOR HEAVY (HIGH ATOMIC WEIGHT) Sixpak

MATERIALS THE CENTER-OF-MASS AND LAB SYSTEMS ARE ALMOST IDENTICAL, Sixpak

SINCE IN THIS CASE THE CENTER-OF-MASS ENERGY WILL BE MUCH SMALLER Sixpak

THAN THE INCIDENT ENERGY. FOR A PROCESS SUCH AS ELASTIC SCATTERING Sixpak

WHERE FOR HEAVY MATERIALS THE SECONDARY ENERGY, EP, WILL ALWAYS Sixpak

BE A LARGE FRACTION OF THE INCIDENT ENERGY, THIS ASSUMPTION IS Sixpak

VALID. HOWEVER, FOR THE TYPICAL REACTIONS INCLUDED IN MF=6 THIS Sixpak

IS NOT ALWAYS TRUE - IN MANY OF THESE CASES THE SECONDARY ENERGY Sixpak

CAN EXTEND ALL THE WAY DOWN TO ZERO, AND IN PARTICULAR IT CAN Sixpak

BE SMALL COMPARED TO THE CENTER-OF-MASS ENERGY - WHICH MAKES THE Sixpak

TRANSFORMATION FROM CENTER-OF-MASS TO LAB IMPORTANT. THEREFORE Sixpak

GENERALLY TO TREAT MF=6 DATA WE MUST CONSIDER THIS TRANSFORMATION. Sixpak

Sixpak

THE FOLLOWING DISCUSSING ONLY APPLIES TO SPECTRA THAT MAY BE Sixpak

OUTPUT IN MF=5 = ONLY DATA FOR NEUTRONS INCIDENT AND EMITTED - Sixpak

IN PARTICULAR THE FOLLOWING DEFINITIONS ARE NOT GENERAL - THEY Sixpak

ARE ONLY VALID FOR INCIDENT AND EMITTED NEUTRONS. Sixpak

Sixpak

DOUBLE DIFFERENTIAL DATA IN MF=6 MAY BE GIVEN IN EITHER THE LAB Sixpak

OR C.M. SYSTEM. SIMILARLY ANGULAR DISTRIBUTIONS IN MF=4 MAY BE Sixpak

GIVEN IN EITHER THE LAB OR C.M. SYSTEM. IN CONTRAST ENERGY Sixpak

SPECTRA IN MF=5 CAN ONLY BE GIVEN IN THE LABORATORY SYSTEM. Sixpak

Sixpak

THE ANGULAR DISTRIBUTIONS OUTPUT BY THIS CODE IN MF=4 ARE IN THE Sixpak

SAME SYSTEM IN WHICH THEY ARE GIVEN IN MF=6 - EITHER LAB OR Sixpak

CENTER-OF-MASS SYSTEM. Sixpak

Sixpak

THE ENERGY SPECTRA OUTPUT BY THIS CODE IN MF=5 MUST BE IN THE LAB Sixpak

SYSTEM - THIS IS THE ONLY ALLOWED FORM FOR MF=5 DATA. Sixpak

Sixpak

FOR MF=6 SPECTRA GIVEN IN THE LAB SYSTEM THIS MERELY REQUIRES Sixpak

COPYING THE GIVEN SPECTRA TO MF=5 OUTPUT. Sixpak

Sixpak

FOR MF=6 SPECTRA GIVEN IN THE CENTER-OF-MASS SYSTEM ONLY FIRST Sixpak

ORDER CORRECTIONS IN THE SPECTRA AND USED AND THEY ARE THEN Sixpak

OUTPUT IN MF=5 AS IN THE LAB SYSTEM - THE FIRST ORDER CORRECTIONS Sixpak

ARE DESCRIBED BELOW. Sixpak

Sixpak

DEFINING, Sixpak

MM = CENTER OF MASS MOTION Sixpak

CM = OUTGOING (EMITTED) PARTICLE IN CENTER OF MASS Sixpak

LAB = OUTGOING (EMITTED) PARTICLE IN LAB Sixpak

THETA = CM SCATTERING ANGLE RELATIVE TO INCIDENT DIRECTION Sixpak

COS(CM) = COSINE OF THE CM SCATTERING ANGLE Sixpak

Sixpak

FOR NEUTRONS INCIDENT WITH AN ENERGY, E, AND THEREFORE A SPEED, Sixpak

Sixpak

VN(E) = 2*SQRT(E)/MASS(IN) Sixpak

Sixpak

THE CENTER-OF-MASS SPEED IS GIVEN BY, Sixpak

Sixpak

V(MM) = VN(E)/(1 + A) Sixpak

Sixpak

AND THE CENTER OF MASS ENERGY BY, Sixpak

Sixpak

E(MM) = 1/2*MASS(IN)*V(MM)**2 Sixpak

= 1/2*MASS(IN)*VN(E)**2/(1 + A)**2 Sixpak

= E/(1 + A)**2 Sixpak

Sixpak

FOR DISTRIBUTIONS GIVEN IN MF=6 IN THE CM, THE SPEED, V(CM), Sixpak

SHOULD BE VECTORIALLY ADDED TO THAT OF OUTGOING PARTICLES TO Sixpak

DEFINE THE OUTGOING PARTICLES LAB VELOCITY, AND IN TURN IT'S Sixpak

ENERGY, Sixpak

Sixpak

V(LAB)*COS(LAB) = V(MM) + V(CM)*COS(CM) Sixpak

V(LAB)*SIN(LAB) = V(CM)*SIN(CM) Sixpak

Sixpak

V(LAB)**2 = V(MM)**2 + V(CM)**2 + 2*COS(CM)*V(MM)*V(CM) Sixpak

Sixpak

EP(LAB) = 0.5*MASS(OUT)*V(LAB)**2 Sixpak

Sixpak

= E(MM) + EP(CM) + 2*COS(CM)*SQRT(E(MM)*EP(CM)) Sixpak

Sixpak

WE CAN ALSO DEFINE THE REVERSE TRANSFORMATION USING, Sixpak

Sixpak

V(CM)*COS(CM) = V(LAB)*COS(LAB) - V(MM) Sixpak

V(CM)*SIN(CM) = V(LAB)*SIN(LAB) Sixpak

Sixpak

V(CM)**2 = V(MM)**2 + V(LAB)**2 - 2*COS(LAB)*V(MM)*V(LAB) Sixpak

Sixpak

EP(CM) = 0.5*MASS(OUT)*V(CM)**2 Sixpak

Sixpak

= E(MM) + EP(LAB) - 2*COS(LAB)*SQRT(E(MM)*EP(LAB)) Sixpak

Sixpak

WE CAN DEFINE COS(LAB) FROM THE RELATIONSHIP, Sixpak

Sixpak

V(LAB)*COS(LAB) = V(MM) + V(CM)*COS(CM) Sixpak

Sixpak

COS(LAB) =[V(MM) + V(CM)*COS(CM)]/V(LAB) Sixpak

Sixpak

[V(MM) + V(CM)*COS(CM)] Sixpak

COS(LAB) =--------------------------------------------- Sixpak

SQRT[V(MM)**2+V(CM)**2+2*COS(CM)*V(MM)*V(CM)] Sixpak

Sixpak

OR COS(CM) FROM THE RELATIONSHIP, Sixpak

Sixpak

V(CM)*COS(CM) = V(LAB)*COS(LAB) - V(MM) Sixpak

Sixpak

COS(CM) =[V(LAB)*COS(LAB) - V(MM)]/V(CM) Sixpak

Sixpak

[V(LAB)*COS(LAB) - V(MM)] Sixpak

COS(CM) =------------------------------------------------ Sixpak

SQRT[V(LAB)**2+V(CM)**2-2*COS(LAB)*V(LAB)*V(MM)] Sixpak

Sixpak

THE JACOBIAN CAN BE DEFINED FROM, Sixpak

Sixpak

V(LAB)*COS(LAB) = V(MM) + V(CM)*COS(CM) Sixpak

Sixpak

J = D[COS(CM)]/D[COS(LAB)] = V(LAB)/V(CM) Sixpak

= SQRT[EP(LAB)/EP(CM)] Sixpak

Sixpak

WITH THESE DEFINITIONS OF EP(LAB) AND COS(LAB) IN TERMS OF E(MM), Sixpak

EP(CM) AND COS(CM) IT IS POSSIBLE TO PERFORM A POINT-BY-POINT Sixpak

TRANSFORMATION OF DISTRIBUTIONS FROM THE CM TO LAB SYSTEM USING Sixpak

THESE DEFINITIONS - OR IF WE WISHED WE COULD PERFORM THE REVERSE Sixpak

TRANSFORMATION USING THE ABOVE RELATIONSHIPS AND THE IDENTITY, Sixpak

Sixpak

F(E,EP(LAB),COS(LAB))*D(COS(LAB))=F(E,EP(CM),COS(CM))*D(COS(CM)) Sixpak

Sixpak

THIS IS NOT WHAT WILL BE DONE HERE, SINCE WE WILL ONLY BE Sixpak

INTERESTED IN THE ZEROTH ORDER MOMENTS OF THESE DISTRIBUTIONS, Sixpak

BUT WE WILL BE INTERESTED IN DEFINING THOSE MOMENTS IN THE Sixpak

LAB SYSTEM IN TERMS OF MF=6 SPECTRA GIVEN IN THE CM SYSTEM USING, Sixpak

Sixpak

F(E,EP(LAB),COS(LAB)) = F(E,EP(CM),COS(CM))*J Sixpak

Sixpak

THE LIMITS OF EP(LAB) ARE DEFINED BY SETTING COS(CM) = +1 OR -1, Sixpak

Sixpak

EP(LAB) = (SQRT(EP(CM)) + SQRT(E(MM)))**2 FOR COS(CM) = +1 Sixpak

= (SQRT(EP(CM)) - SQRT(E(MM)))**2 FOR COS(CM) = -1 Sixpak

Sixpak

IN THIS FORM WE CAN SEE THAT AS LONG AS THE SECONDARY ENERGY IN Sixpak

THE CENTER-OF-MASS SYSTEM, EP(CM), IS MUCH LARGER THAN THE Sixpak

ENERGY OF THE CENTER-OF-MASS, E(MM), THE CENTER-OF-MASS AND LAB Sixpak

ENERGIES WILL BE ALMOST EQUAL - SIMILARLY FOR THE COSINE, IN Sixpak

THIS CASE COS(LAB) AND COS(CM) WILL BE ALMOST EQUAL - HOWEVER, Sixpak

FOR THE MF=6 DATA WE CANNOT ASSUME THAT THIS IS TRUE. Sixpak

Sixpak

TO FIRST ORDER THE ANGULAR DEPENDENCE CAN BE IGNORED, Sixpak

Sixpak

EP(LAB) = E(MM) + EP(CM) Sixpak

Sixpak

ALL THIS SAYS IS THAT TO FIRST ORDER THE EFFECT OF TRANSFORMING Sixpak

FROM THE CM TO LAB SYSTEM IS TO INCREASE THE ENERGY OF THE Sixpak

EMITTED PARTICLE IN THE CENTER-OF-MASS SYSTEM BY THE ENERGY OF Sixpak

THE CENTER-OF-MASS TO DEFINE THE LAB ENERGY. Sixpak

Sixpak

NOT ONLY THE ENERGY, BUT ALSO THE SPECTRA MUST BE TRANSFORMED. Sixpak

STARTING FROM THE DOUBLE DIFFERENTIAL DATA IN THE LAB SYSTEM, Sixpak

F(E,EP,COS(LAB)), WE CAN DEFINE THE LAB SCALAR SPECTRUM AS, Sixpak

Sixpak

G0(E,EP) = INTEGRAL F(E,EP,COS(LAB))*D(COS(LAB)) Sixpak

Sixpak

THIS IS THE NORMAL CALCULATION DEFINED ABOVE AND USED FOR DATA Sixpak

GIVEN IN THE LAB SYSTEM. Sixpak

Sixpak

STARTING FROM DATA IN THE CENTER OF MASS SYSTEM F(E,EP,COS(CM)), Sixpak

WE CAN USE THE RELATIONSHIP, Sixpak

Sixpak

F(E,EP,COS(LAB))*D(COS(LAB)) = F(E,EP,COS(CM))*J*D(COS(LAB)) Sixpak

Sixpak

J = SQRT(EP(LAB)/EP(CM)) - THE JACOBIAN Sixpak

Sixpak

= E(MM)/EP(CM) + 1 + 2*COS(CM)*SQRT(E(MM)/EP(CM)) Sixpak

Sixpak

AS IN THE CASE OF THE ENERGY, IN THIS FORM WE CAN SEE THAT AS Sixpak

LONG AS THE SECONDARY ENERGY IN THE CENTER-OF-MASS SYSTEM, Sixpak

EP(CM), IS LARGE COMPARED TO THE CENTER-OF-MASS ENERGY, E(MM), Sixpak

THE JACOBIAN IS ESSENTIALLY UNITY AND THE CENTER-OF-MASS AND LAB Sixpak

SPECTRA WILL BE VERY SIMILAR - AGAIN, GENERALLY WE CANNOT Sixpak

ASSUME THAT THIS IS TRUE FOR THE MF=6 SPECTRA. Sixpak

Sixpak

THEREFORE WE CAN ALSO DEFINE THE LAB SCALAR SPECTRUM IN TERMS OF Sixpak

THE CM SPECTRUM IN THE FORM, Sixpak

Sixpak

G0(E,EP) = INTEGRAL F(E,EP,COS(CM))*J*D(COS(LAB)) Sixpak

Sixpak

CONSISTENT WITH THE ABOVE ASSUMPTION THAT THE ANGULAR DEPENDENCE Sixpak

OF EP(LAB) CAN BE IGNORED THE JACOBIAN WILL NOT BE USED IN Sixpak

PERFORMING THESE INTEGRALS - IN WHICH CASE THE INTEGRAL REDUCES Sixpak

TO EXACTLY THE SAME FORM AS IF THE DATA WERE IN THE LAB SYSTEM. Sixpak

Sixpak

IT SHOULD BE NOTED THAT SINCE IN THIS CASE THE MF=4 ANGULAR Sixpak

DISTRIBUTIONS ARE GIVEN IN THE CM SYSTEM AND WHEN USED IN ANY Sixpak

APPLICATION THEY WILL BE TRANSFORMED TO THE LAB SYSTEM - WHEN Sixpak

THIS IS DONE THE JACOBIAN WILL BE APPLIED. Sixpak

Sixpak

IN THIS CODE WHERE WE ARE MOSTLY CONCERNED WITH CONSERVING THE Sixpak

NUMBER OF EMITTED PARTICLES AND AVERAGE ENERGIES THE NEUTRON Sixpak

SPECTRA OUTPUT IN MF=5 WILL NOT BE COMPLETELY CONVERTED TO THE Sixpak

LAB SYSTEM - ONLY FIRST ORDER CORRECTIONS WILL BE INCLUDED BY Sixpak

INCREASING THE EMITTED PARTICLE ENERGY BY THE CENTER OF MASS Sixpak

ENERGY, I.E., FOR A CENTER OF MASS SPECTRUM TABULATED AT CENTER Sixpak

OF MASS ENERGIES EP(CM) THESE WILL ALL BE UNIFORMLY INCREASED Sixpak

BY E(MM) TO ACCOUNT FOR THE CENTER OF MASS MOTION - THE SPECTRA Sixpak

WILL NOT BE MODIFIED BY THE JACOBIAN FACTOR SQRT(EP(LAB)/EP(CM)) Sixpak

SINCE THIS WOULD REQUIRE A DETAILED TRANSFORMATION IN ENERGY AND Sixpak

COS(THETA) SPACE - WHICH IS JUDGED NOT TO BE WORTH PERFORMING Sixpak

WITHIN THE LIMITS OF WHERE THE OUTPUT FROM THIS CODE IS INTENDED Sixpak

TO BE USED. Sixpak

Sixpak

SINCE THE ANGULAR DISTRIBUTION IS ALWAYS OUTPUT IN THE SAME Sixpak

SYSTEM AS WHICH IT IS GIVEN IN MF=6, NO TRANSFORMATION IS Sixpak

REQUIRED FOR THE MF=4 OUTPUT. Sixpak

Sixpak

WHEN USED IN LOW ENERGY APPLICATIONS (E.G., FISSION REACTORS) THE Sixpak

HIGH ENERGY SPECTRA PRESENTED IN MF=6 WILL BE MOSTLY IMPORTANT Sixpak

SIMPLY IN CONSERVING PARTICLES, (E.G., AS IN (N,2N)) AND ENERGY Sixpak

AND THE DETAILS OF THE CORRELATION AND GROSS ENERGY SPECTRA WILL Sixpak

NOTE PLAY THAT IMPORTANT A ROLE. IN THIS CASE THE SPECTRA OUTPUT Sixpak

BY THIS PROGRAM IN MF=5 SHOULD BE ADEQUATE. Sixpak

Sixpak

PLOTTAB FORMATTED OUTPUT Sixpak

================================================================== Sixpak

THIS PROGRAM CONTAINS ROUTINES TO PRODUCE OUTPUT THAT CAN BE USED Sixpak

AS INPUT TO THE PLOTTAB CODE TO OBTAIN GRAPHIC RESULTS. Sixpak

Sixpak

THESE ROUTINES ARE DESIGNED ONLY FOR USE BY THE AUTHOR TO CHECK Sixpak

THIS CODE. USERS ARE ASKED NOT TO ACTIVATE OR TRY TO USE THESE Sixpak

ROUTINES. UNLESS YOU COMPLETELY UNDERSTAND THIS CODE THE RESULTS Sixpak

CAN BE UNRELIABLE IF YOU ACTIVATE THESE ROUTINES. Sixpak

Sixpak

INPUT FILES Sixpak

================================================================== Sixpak

UNIT DESCRIPTION Sixpak

---- ----------- Sixpak

2 INPUT LINES (BCD - 80 CHARACTERS/RECORD) Sixpak

10 ORIGINAL ENDF/B DATA (BCD - 80 CHARACTERS/RECORD) Sixpak

Sixpak

OUTPUT FILES Sixpak

================================================================== Sixpak

UNIT DESCRIPTION Sixpak

---- ----------- Sixpak

3 OUTPUT REPORT (BCD - 120 CHARACTERS/RECORD) Sixpak

11 ENDF/B DATA MF=4 (BCD - 80 CHARACTERS/RECORD) Sixpak

12 ENDF/B DATA MF=5 (BCD - 80 CHARACTERS/RECORD) Sixpak

14 ENDF/B DATA MF=15 (BCD - 80 CHARACTERS/RECORD) Sixpak

17 ENDF/B DATA MF=12 (BCD - 80 CHARACTERS/RECORD) Sixpak

18 ENDF/B DATA MF=14 (BCD - 80 CHARACTERS/RECORD) Sixpak

15 PLOTTAB INPUT PARAMETERS (BCD - 80 CHARACTERS/RECORD) Sixpak

16 PLOTTAB FORMATTED OUTPUT (BCD - 80 CHARACTERS/RECORD) Sixpak

Sixpak

SCRATCH FILES Sixpak

================================================================== Sixpak

NONE Sixpak

Sixpak

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2) Sixpak

================================================================== Sixpak

UNIT FILE NAME Sixpak

---- ---------- Sixpak

2 SIXPAK.INP Sixpak

3 SIXPAK.LST Sixpak

10 ENDFB.IN Sixpak

11 ENDFB.MF4 Sixpak

12 ENDFB.MF5 Sixpak

14 ENDFB.M15 Sixpak

17 ENDFB.M12 Sixpak

18 ENDFB.M14 Sixpak

15 PLOTTAB.INP Sixpak

16 PLOTTAB.CUR Sixpak

Sixpak

Sixpak

INPUT PARAMETERS Sixpak

================================================================== Sixpak

LINE COLS. DESCRIPTION Sixpak

---- ----- ----------- Sixpak

1 1-60 ENDF/B INPUT DATA FILENAME Sixpak

(STANDARD OPTION = ENDFB.IN) Sixpak

2-N 1-6 MINIMUM MAT FOR REQUESTED RANGE Sixpak

9-11 MINIMUM MT FOR REQUESTED RANGE Sixpak

12-17 MAXIMUM MAT FOR REQUESTED RANGE Sixpak

20-22 MAXIMUM MT FOR REQUESTED RANGE Sixpak

Sixpak

LEAVE THE DEFINITION OF THE FILENAME BLANK - THE PROGRAM WILL Sixpak

THEN USE THE STANDARD FILENAME (ENDFB.IN). Sixpak

Sixpak

UP TO 100 MAT/MT RANGES MAY BE SPECIFIED. THE LIST OF RANGES IS Sixpak

TERMINATED BY A BLANK LINE. IF THE FIRST INPUT LINE IS COMPLETELY Sixpak

BLANK ALL DATA WILL BE PROCESSED. Sixpak

Sixpak

EXAMPLE INPUT NO. 1 Sixpak

------------------- Sixpak

PROCESS ALL MF=6 DATA ON AN ENDF/B TAPE. USE THE STANDARD INPUT Sixpak

DATA FILENAME ENDFB.IN IN THIS CASE THE USER CAN EITHER EXPLICITLY Sixpak

SPECIFY THE FILENAME AND MAT/MT RANGE BY THE FOLLOWING 2 INPUT Sixpak

LINES, Sixpak

Sixpak

ENDFB.IN Sixpak

1 1 9999 999 Sixpak

(BLANK LINE, TERMINATES REQUEST LIST) Sixpak

Sixpak

OR BY INPUTTING 2 BLANK LINE = PROCESS EVERYTHING. Sixpak

Sixpak

EXAMPLE INPUT NO. 2 Sixpak

------------------- Sixpak

PROCESS BE-9, MAT=425, MT=16. READ THE DATA FROM ENDFB6\BE9. Sixpak

IN THIS CASE THE FOLLOWING 3 INPUT LINES ARE REQUIRED, Sixpak

Sixpak

ENDFBB6\BE9 Sixpak

425 16 425 16 Sixpak

(BLANK LINE, TERMINATES REQUEST LIST) Sixpak

Sixpak

EXAMPLE INPUT NO. 3 Sixpak

------------------- Sixpak

PROCESS ALL MT=16 (N,2N) DATA. THIS CAN BE DONE BY SPECIFYING THE Sixpak

MAXIMUM MAT RANGE = 1 TO 9999, AND MT=16 FOR THE MINIMUM AND Sixpak

MAXIMUM MT RANGE. READ THE DATA FROM ENDFB6\K300. IN THIS CASE Sixpak

CASE THE FOLLOWING 3 INPUT LINES ARE REQUIRED, Sixpak

Sixpak

ENDFB6\K300 Sixpak

1 16 9999 16 Sixpak

(BLANK LINE, TERMINATES REQUEST LIST) Sixpak

Sixpak

======================================================================= Sixpak

======================================================================= Virgin

Virgin

PROGRAM VIRGIN Virgin

VERSION 76-1 (NOVEMBER 1976) Virgin

VERSION 84-1 (JUNE 1984) *DOUBLE PRECISION ENERGY Virgin

VERSION 86-1 (JANUARY 1986)*FORTRAN-77/H VERSION Virgin

VERSION 88-1 (JULY 1988) *OPTION...INTERNALLY DEFINE ALL I/O Virgin

FILE NAMES (SEE, SUBROUTINE FILEIO Virgin

FOR DETAILS). Virgin

*IMPROVED BASED ON USER COMMENTS. Virgin

VERSION 89-1 (JANUARY 1989)*PSYCHOANALYZED BY PROGRAM FREUD TO Virgin

INSURE PROGRAM WILL NOT DO ANYTHING Virgin

CRAZY. Virgin

*UPDATED TO USE NEW PROGRAM CONVERT Virgin

KEYWORDS. Virgin

*ADDED LIVERMORE CIVIC COMPILER Virgin

CONVENTIONS. Virgin

VERSION 92-1 (JANUARY 1992)*COMPLETE RE-WRITE Virgin

*OUTPUT IN PLOTTAB FORMAT Virgin

*UP TO 2000 THICKNESSES Virgin

*INCREASED INCORE PAGE SIZE TO 6000 Virgin

CROSS SECTION POINTS Virgin

*ADDED PHOTON CALCULATIONS Virgin

*ADDED BLACKBODY SPECTRUM Virgin

*ADDED MULTIPLE LAYERS Virgin

*ADDED SPATIALLY DEPENDENT DENSITY Virgin

*ADDED FORTRAN SAVE OPTION Virgin

*COMPLETELY CONSISTENT I/O ROUTINES - Virgin

TO MINIMIZE COMPUTER DEPENDENCE. Virgin

VERSION 92-2 (MAY 1992) *CORRECTED TO HANDLE MULTIGROUP CROSS Virgin

SECTIONS AS INPUT IN ENDF/B FORMAT. Virgin

VERSION 96-1 (JANUARY 1996) *COMPLETE RE-WRITE Virgin

*IMPROVED COMPUTER INDEPENDENCE Virgin

*ALL DOUBLE PRECISION Virgin

*ON SCREEN OUTPUT Virgin

*UNIFORM TREATMENT OF ENDF/B I/O Virgin

*IMPROVED OUTPUT PRECISION Virgin

*DEFINED SCRATCH FILE NAMES Virgin

VERSION 99-1 (MARCH 1999) *CORRECTED CHARACTER TO FLOATING Virgin

POINT READ FOR MORE DIGITS Virgin

*UPDATED TEST FOR ENDF/B FORMAT Virgin

VERSION BASED ON RECENT FORMAT CHANGE Virgin

*GENERAL IMPROVEMENTS BASED ON Virgin

USER FEEDBACK Virgin

VERS. 2000-1 (FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON Virgin

USER FEEDBACK Virgin

VERS. 2002-1 (MAY 2002) *OPTIONAL INPUT PARAMETERS Virgin

VERS. 2004-1 (MARCH 2004) *ADDED INCLUDE FOR COMMON Virgin

*UP TO 2000 THICKNESSES Virgin

*INCREASED INCORE PAGE SIZE TO 12,000 Virgin

Virgin

OWNED, MAINTAINED AND DISTRIBUTED BY Virgin

------------------------------------ Virgin

THE NUCLEAR DATA SECTION Virgin

INTERNATIONAL ATOMIC ENERGY AGENCY Virgin

P.O. BOX 100 Virgin

A-1400, VIENNA, AUSTRIA Virgin

EUROPE Virgin

Virgin

ORIGINALLY WRITTEN BY Virgin

------------------------------------ Virgin

DERMOTT E. CULLEN Virgin

UNIVERSITY OF CALIFORNIA Virgin

LAWRENCE LIVERMORE NATIONAL LABORATORY Virgin

L-159 Virgin

P.O. BOX 808 Virgin

LIVERMORE, CA 94550 Virgin

U.S.A. Virgin

TELEPHONE 925-423-7359 Virgin

E. MAIL CULLEN1@LLNL.GOV Virgin

WEBSITE HTTP://WWW.LLNL.GOV/CULLEN1 Virgin

Virgin

PURPOSE Virgin

------- Virgin

THIS PROGRAM IS DESIGNED TO CALCULATE UNCOLLIDED (I.E. VIRGIN) Virgin

FLUX AND REACTIONS DUE TO TRANSMISSION OF A MONODIRECTIONAL Virgin

BEAM OF NEUTRONS THROUGH ANY THICKNESS OF MATERIAL. IN ORDER Virgin

TO SIMULATE AN EXPERIMENTAL MEASUREMENT THE RESULTS ARE GIVEN Virgin

AS INTEGRALS OVER ENERGY TALLY GROUPS (AS OPPOSED TO POINTWISE Virgin

IN ENERGY). BY TAKING THE RATIO OF REACTIONS TO FLUX IN EACH Virgin

GROUP AN EQUIVALENT SPATIALLY DEPENDENT GROUP AVERAGED CROSS Virgin

SECTION IS CALCULATED BY THE PROGRAM. Virgin

Virgin

EVALUATED DATA Virgin

-------------- Virgin

THE EVALUATED DATA MUST BE IN THE ENDF/B FORMAT. HOWEVER IT Virgin

MUST BE LINEAR-LINEAR INTERPOLABLE IN ENERGY-CROSS SECTION Virgin

BETWEEN TABULATED POINTS. SINCE ONLY CROSS SECTIONS (FILE 3 OR 23) Virgin

ARE USED, THIS PROGRAM WILL WORK ON ANY VERSION OF ENDF/B Virgin

(I.E. ENDF/B-I, II, III, IV, V OR VI). Virgin

Virgin

RELATED COMPUTER CODES Virgin

---------------------- Virgin

IN ORDER TO CONVERT ENDF/B DATA TO THE FORM REQUIRED BY THIS CODE Virgin

THE FOLLOWING COMPUTER CODES MAY BE USED, Virgin

Virgin

LINEAR - CONVERT FROM GENERAL ENDF/B INTERPOLATION TO LINEAR- Virgin

LINEAR INTERPOLATION. Virgin

RECENT - ADD THE RESONANCE CONTRIBUTION TO TABULATED BACKGROUND Virgin

CROSS SECTIONS TO OBTAIN LINEAR-LINEAR INTERPOLABLE Virgin

RESULTS. Virgin

SIGMA1 - DOPPLER BROADEN CROSS SECTION TO OBTAIN LINEAR-LINEAR Virgin

INTERPOLABLE RESULTS. Virgin

MIXER - MIX INDIVIDUAL MATERIALS TOGETHER TO DEFINE COMPOSITE Virgin

MIXTURES, E.G., COMBINE MATERIALS TO DEFINE STAINLESS Virgin

STELL. Virgin

Virgin

IN ORDER TO PLOT THE OUTPUT RESULTS OF THIS CODE USE PROGRAM Virgin

PLOTTAB. Virgin

Virgin

COPIES OF ANY OR ALL OF THESE CODES MAY BE OBTAINED FROM D.E. Virgin

CULLEN AT THE ABOVE ADDRESS. Virgin

Virgin

OUTPUT FORMAT Virgin

------------- Virgin

FOR ALL VERSIONS OF THIS PROGRAM PRIOR TO VERSION 92-1 OUTPUT WAS Virgin

IN TABULAR FORM. Virgin

Virgin

FOR VERSION 92-1 AND LATER VERSIONS OF THIS CODE ALL OUTPUT IS IN Virgin

THE PROGRAM PLOTTAB FORMAT TO ALLOW RESULTS TO BE EASILY PLOTTED. Virgin

FOR A COPY OF PROGRAM PLOTTAB CONTACT D.E. CULLEN AT THE ABOVE Virgin

ADDRESS. Virgin

Virgin

TALLY GROUPS Virgin

------------ Virgin

THE TALLY GROUP STRUCTURE MAY BE ANY SET OF MONONTONICALLY Virgin

INCREASING ENERGY BOUNDARIES. THERE MAY BE UP TO 2000 TALLY Virgin

GROUPS. BY USING THE INPUT PARAMETERS THE USER MAY SPECIFY ANY Virgin

ARBITRARY TALLY GROUP STRUCTURE OR SELECT ONE OF THE FOLLOWING Virgin

BUILT-IN GROUP STRUCTURES. Virgin

Virgin

(1) TART 175 GROUPS (INPUT 0) Virgin

(2) ORNL 50 GROUPS (INPUT -1) Virgin

(3) ORNL 126 GROUPS (INPUT -2) Virgin

(4) ORNL 171 GROUPS (INPUT -3) Virgin

(5) SAND-II 620 GROUPS...UP TO 18 MEV (INPUT -4) Virgin

(6) SAND-II 640 GROUPS...UP TO 20 MEV (INPUT -5) Virgin

(7) WIMS 69 GROUPS (INPUT -6) Virgin

(8) GAM-I 68 GROUPS (INPUT -7) Virgin

(9) GAM-II 99 GROUPS (INPUT -8) Virgin

(10) MUFT 54 GROUPS (INPUT -9) Virgin

(11) ABBN 28 GROUPS (INPUT -10) Virgin

Virgin

INCIDENT SPECTRUM Virgin

----------------- Virgin

THE INCIDENT SPECTRUM MAY BE ANY TABULATED FUNCTION THAT IS Virgin

GIVEN BY A SET OF POINTS THAT IS MONOTONICALLY INCREASING IN Virgin

ENERGY AND LINEAR-LINEAR INTERPOLABLE IN ENERGY-SPECTRUM Virgin

BETWEEN TABULATED POINTS. THERE IS NO LIMIT TO THE NUMBER OF Virgin

POINTS USED TO DESCRIBE THE SPECTRUM. THERE ARE FIVE BUILT-IN Virgin

OPTIONS FOR THE SPECTRUM. Virgin

Virgin

(1) CONSTANT...ENERGY INDEPENDENT (INPUT 0) Virgin

(2) 1/E (INPUT 1) Virgin

(3) BLACKBODY - PHOTON SPECTRUM Virgin

(4) BLACKBODY - ENERGY SPECTRUM (E TIMES THE PHOTON SPECTRUM) Virgin

(5) TRANSMITTED SPECTRUM FROM PREVIOUS CASE Virgin

Virgin

NORMALIZATION OF SPECTRUM Virgin

------------------------- Virgin

ANY INCIDENT SPECTRUM, EITHER READ AS INPUT OR ONE OF THE Virgin

BUILT-IN SPECTRA, WILL BE NORMALIZED TO UNITY WHEN INTEGRATED Virgin

OVER THEIR ENTIRE ENERGY RANGE. Virgin

Virgin

TRANSMITTED SPECTRA WILL NOT BE RE-NORMALIZED, SINCE IT ALREADY Virgin

INCLUDES THE NORMALIZATION OF THE INCIDENT SPECTRUM. Virgin

Virgin

NOTE, INCIDENT SPECTRA IS NORMALIZED TO UNITY OVER THEIR ENTIRE Virgin

ENERGY RANGE - NOT OVER THE ENERGY RANGE OF THE GROUPS. IF THE Virgin

ENERGY RANGE OF THE GROUPS IS LESS THAN THAT OF THE SPECTRUM Virgin

ONLY THAT PORTION OF THE SPECTRUM WILL BE USED AND THIS WILL Virgin

NOT BE RE-NORMALIZED TO UNITY. Virgin

Virgin

COMPOSITION OF A LAYER Virgin

---------------------- Virgin

YOU MAY RUN PROBLEMS INVOLVING Virgin

1) A LAYER OF UNIFORM DENSITY - DENSITY FOR ATTENUATION IS THAT Virgin

OF THE TOTAL. DENSITY FOR REACTIONS IS THAT OF THE REACTION. Virgin

2) A LAYER OF UNIFORM DENSITY - DENSITY IS THE SUM OF THE TOTAL Virgin

AND REACTION DENSITIES - THE SUM OF THE CROSS SECTIONS IS Virgin

USED FOR ATTENUATION AND REACTIONS. Virgin

3) A LAYER OF VARYING DENSITY BASED ON A UNIFORM TOTAL DENSITY Virgin

PLUS A VARIATION BETWEEN 0 AND A MAXIMUM BASED ON THE Virgin

REACTION DENSITY - 0 AT 0 THICKNESS AND MAXIMUM AT MAXIMUM Virgin

THICKNESS. IN THIS CASE THE AVERAGE REACTION DENSITY IS EQUAL Virgin

TO THE INPUT REACTION DENSITY. THE VARIATION IN REACTION Virgin

DENSITY CAN BE LINEAR, SQUARE OR CUBIC. Virgin

4) A LAYER OF VARYING DENSITY BASED ON A TOTAL DENSITY WHICH Virgin

VARYING FROM MAXIMUM AT 0 THICKNESS TO 0 AT MAXIMUM THICKNESS Virgin

PLUS A REACTION DENSITY WHICH VARIES FROM 0 AT 0 THICKNESS Virgin

TO MAXIMUM AT MAXIMUM THICKNESS. IN THIS CASE THE AVERAGE Virgin

DENSITY OF THE TOTAL AND REACTION WILL BOTH BE EQUAL TO THE Virgin

INPUT TOTAL AND REACTION DENSITIES. THE VARIATION IN TOTAL Virgin

AND REACTION DENSITY CAN BE LINEAR, SQUARE OR CUBIC. Virgin

Virgin

IN THE FIRST CASE THE TWO REQUESTED CROSS SECTIONS ARE CONSIDERED Virgin

TO BE INDEPENDENT - THE TOTAL CROSS SECTION IS USED TO CALCULATE Virgin

ATTENUATION AND THE REACTION CROSS SECTION IS USED TO CALCULATE Virgin

REACTIONS, E.G., TRANSMISSION THROUGH NATURAL URANIUM (THE TOTAL Virgin

CROSS SECTION SHOULD BE THAT OF NATURAL URANIUM) AND REACTIONS Virgin

IN A U-235 DETECTOR (THE REACTION CROSS SECTION SHOULD BE THAT OF Virgin

U-235). Virgin

Virgin

IN THE OTHER THREE CASES THE TWO REQUESTED CROSS SECTIONS ARE Virgin

TREATED AS TWO CONSTITUENTS OF A MIXTURE OF TWO MATERIALS AND Virgin

THE TWO CROSS SECTIONS ARE USED BOTH TO DEFINE A TOTAL CROSS Virgin

SECTION FOR ATTENUATION AND A REACTION CROSS SECTION TO DEFINE Virgin

REACTIONS. IN THESE CASES THE MIXTURE WILL VARY CONTINUOUSLY, Virgin

E.G., IN CASE 4) HALF WAY THROUGH THE LAYER THE COMPOSITION WILL Virgin

BE 1/2 THE MATERIAL DEFINED BY THE TOTAL AND 1/2 THE MATERIAL Virgin

BASED ON THE REACTION. IN THESE CASES RATHER THAN THINKING OF Virgin

THE TWO CROSS SECTIONS AS A TOTAL AND REACTION CROSS SECTION, Virgin

IT IS BETTER TO THINK OF THEM AS THE TOTAL CROSS SECTIONS FOR Virgin

MATERIALS A AND B AND THE CALCULATED REACTIONS WILL BE BASED Virgin

ON THESE TWO TOTAL CROSS SECTIONS. Virgin

Virgin

MULTIPLE LAYERS Virgin

--------------- Virgin

THIS CODE MAY BE USED TO RUN EITHER A NUMBER OF INDEPENDENT Virgin

PROBLEMS, EACH INVOLVING TRANSMISSION THROUGH A SINGLE LAYER OF Virgin

MATERIAL, OR TRANSMISSION THROUGH A NUMBER OF LAYERS ONE AFTER Virgin

THE OTHER. Virgin

Virgin

IN THE CASE OF MULTIPLE LAYERS, ONE LAYER AFTER ANOTHER, THE Virgin

TRANSMITTED ENERGY DEPENDENT SPECTRUM IS USED AS THE INCIDENT Virgin

SPECTRUM FOR THE NEXT LAYER. THERE IS NO LIMIT TO THE NUMBER Virgin

OF LAYERS WHICH MAY BE USED - EACH LAYER IS TREATED AS A Virgin

COMPLETELY INDEPENDENT PROBLEM WITH A DEFINED INCIDENT SOURCE, Virgin

AND AS SUCH THE CYCLE OF TRANSMISSION THROUGH EACH LAYER AND Virgin

USING THE TRANSMITTED SPECTRUM AS THE INCIDENT SPECTRUM FOR THE Virgin

NEXT LAYER MAY BE REPEATED ANY NUMBER OF TIMES. Virgin

Virgin

REMEMBER - THE INCIDENT SPECTRUM IS ASSUMED TO BE LINEARLY Virgin

INTERPOLABLE IN ENERGY AND SPECTRUM BETWEEN THE ENERGIES AT Virgin

WHICH IT IS TABULATED. THE TRANSMITTED SPECTRUM WILL BE TABULATED Virgin

AT THE UNION OF ALL ENERGIES OF THE INCIDENT SPECTRUM AND CROSS Virgin

SECTIONS (TOTAL AND REACTION). IN ORDER TO INSURE THE ACCURACY Virgin

OF THE RESULT WHEN PERFORMING MULTIPLE LAYER CALCULATION BE SURE Virgin

TO SPECIFY THE INCIDENT SPECTRUM ON THE FIRST LAYER TO SUFFICIENT Virgin

DETAIL (ENOUGH ENERGY POINTS CLOSELY SPACED TOGETHER) IN ORDER TO Virgin

ALLOW THE TRANSMITTED SPECTRUM TO BE ACCURATELY REPRESENTED BY Virgin

LINEAR INTERPOLATION BETWEEN SUCCESSIVE ENERGY POINTS - THERE IS Virgin

NO LIMIT TO THE NUMBER OF POINTS ALLOWED IN THE INCIDENT SPECTRUM, Virgin

SO IF YOU ARE IN DOUBT, SIMPLY USE MORE ENERGY POINTS TO SPECIFY Virgin

THE INCIDENT SPECTRUM. Virgin

Virgin

RESULT OUTPUT UNITS Virgin

------------------- Virgin

FLUX = EXACTLY AS CALCULATED Virgin

REACTIONS = 1/CM OR 1/GRAM Virgin

AVERAGE = 1/CM - MACROSCOPIC UNITS Virgin

CROSS Virgin

SECTION Virgin

Virgin

THICKNESS AND DENSITY Virgin

--------------------- Virgin

THE UNCOLLIDED CALCULATION ONLY DEPENDS ON THE PRODUCT OF Virgin

THICKNESS AND DENSITY (I.E. GRAMS PER CM SQUARED). THIS FACT Virgin

MAY BE USED TO SIMPLIFY INPUT BY ALLOWING THE THICKNESS AND Virgin

DENSITY TO BE GIVEN EITHER AS CM AND GRAMS/CC RESPECTIVELY Virgin

OR ELSE TO GIVE THICKNESS IN GRAMS/(CM*CM) AND INPUT A Virgin

DENSITY OF 1.0 - OR IN ANY OTHER CONVENIENT UNITS AS LONG AS Virgin

THE PRODUCT OF THICKNESS AND DENSITY IS IN THE CORRECT GRAMS Virgin

PER CENTIMETER SQUARED. Virgin

Virgin

GRAMS/(CM*CM) ARE RELATED TO ATOMS/BARN THROUGH THE RELATIONSHIP Virgin

Virgin

GRAMS/(CM*CM)=(ATOMS/BARN)*(GRAMS/MOLE)*(MOLE/ATOM) Virgin

Virgin

OR... Virgin

Virgin

GRAMS/(CM*CM)=(ATOMS/BARN)*(ATOMIC WEIGHT)/0.602 Virgin

Virgin

CROSS SECTIONS AT A SPACE POINT AND OPTICAL THICKNESS Virgin

----------------------------------------------------- Virgin

THIS PROGRAM ALLOWS LAYERS OF EITHER UNIFORM DENSITY OR Virgin

CONTINUOUSLY VARYING DENSITY. THE DENSITY CAN BE ONE OF THE Virgin

FOLLOWING FORMS, Virgin

1) C = UNIFORM DENSITY Virgin

2) C*2*(X/T) = LINEAR VARIATION FROM 0 TO C Virgin

3) C*(2-2*(X/T)) = LINEAR VARIATION FROM C TO 0 Virgin

4) C*3*(X/T)**2 = SQUARE VARIATION FROM 0 TO C Virgin

5) C*(3-3*(X/T)**2)/2 = SQUARE VARIATION FROM C TO 0 Virgin

6) C*4*(X/T)**3 = CUBIC VARIATION FROM 0 TO C Virgin

7) C*(4-4*(X/T)**3)/3 = CUBIC VARIATION FROM C TO 0 Virgin

Virgin

IN ORDER TO CALCULATE REACTIONS AT A POINT THE MICROSCOPIC Virgin

REACTION CROSS SECTION NEED MERELY BE SCALED BY THESE DENSITIES. Virgin

Virgin

IN ORDER TO CALCULATE TRANSMISSION WE MUST DEFINE THE OPTICAL Virgin

PATH LENGTH WHICH MAY BE DEFINED BY INTEGRATING EACH OF THE Virgin

ABOVE DENSITY FORMS TO FIND, Virgin

1) C*X Virgin

2) C*X*(X/T) Virgin

3) C*X*(2-(X/T)) Virgin

4) C*X*(X/T)**2 Virgin

5) C*X*(3-(X/T)**2)/2 Virgin

6) C*X*(X/T)**3 Virgin

7) C*X*(4-(X/T)**3))/3 Virgin

Virgin

IN ORDER TO CALCULATE TRANSMISSION TO A POINT THE MICROSCOPIC Virgin

TOTAL CROSS SECTION NEED MERELY BE SCALED BY THESE DENSITIES Virgin

TO DEFINE THE OPTICAL PATH LENGTH. Virgin

Virgin

THE VARIATION OF THE DENSITY THROUGH THE LAYER MAY BE DEFINED Virgin

BY SETTING X = 0 OR X = T TO FIND, Virgin

X = 0 X = T Virgin

----- ----- Virgin

1) C C Virgin

2) 0 2*C Virgin

3) 2*C 0 Virgin

4) 0 3*C Virgin

5) 3*C/2 0 Virgin

6) 0 4*C Virgin

7) 4*C/3 0 Virgin

Virgin

THE OPTICAL PATH THROUGH A LAYER OF THICKNESS T MAY BE DEFINED Virgin

FROM THE ABOVE EXPRESSIONS BY SETTING X=T TO FIND THAT IN ALL Virgin

CASES THE ANSWER WILL BY C*T. THE CONSTANTS IN THE ABOVE Virgin

EXPRESSIONS HAVE BEEN INTRODUCED IN ORDER TO FORCE THIS RESULT. Virgin

WITH THESE FACTORS THE OPTICAL PATH LENGTH THROUGH THE LAYER Virgin

WILL EXACTLY CORRESPOND TO AN AVERAGE DENSITY CORRESPONDING TO Virgin

THAT INPUT FOR THE TOTAL AND/OR REACTION, I.E., C CORRESPONDS Virgin

TO THE INPUT DENSITY. Virgin

Virgin

NOTE - FOR THE SAME OPTICAL PATH LENGTHS THROUGH THE LAYER THE Virgin

TRANSMISSION WILL BE EXACTLY THE SAME. HOWEVER, VARYING THE Virgin

DENSITY WILL ALLOW YOU TO MODIFY THE REACTION RATES AT SPECIFIC Virgin

DEPTHS INTO THE LAYER. Virgin

Virgin

COMPUTATION OF INTEGRALS Virgin

------------------------ Virgin

STARTING FROM TOTAL CROSS SECTIONS, REACTION CROSS SECTIONS AND Virgin

A SOURCE SPECTRUM ALL OF WHICH ARE GIVEN IN TABULAR FORM WITH Virgin

LINEAR INTERPOLATION BETWEEN TABULATED POINTS ALL REQUIRED Virgin

INTEGRALS CAN BE DEFINED BY ANALYTICAL EXPRESSIONS INVOLVING Virgin

NOTHING MORE COMPLICATED THAN EXPONENTIALS. THE INTEGRALS THAT Virgin

MUST BE EVALUATED ARE OF THE FORM... Virgin

Virgin

FLUX Virgin

---- Virgin

(INTEGRAL EK TO EK+1) (S(E)* EXP(-XCT(E)*Z)*DE) Virgin

Virgin

REACTIONS Virgin

--------- Virgin

(INTEGRAL EK TO EK+1) (S(E)*XCR(E)*EXP(-XCT(E)*Z)*DE) Virgin

Virgin

WHERE.. Virgin

EK TO EK+1 = LONGEST ENERGY INTERVAL OVER WHICH S(E), XCT(E) AND Virgin

XCR(E) ARE ALL LINEARLY INTERPOLABLE. Virgin

S(E) = ENERGY DEPENDENT WEIGHTING SPECTRUM Virgin

XCR(E) = REACTION CROSS SECTION Virgin

XCT(E) = OPTICAL PATH LENGTH (BASED ON TOTAL CROSS SECTION) Virgin

Z = MATERIAL THICKNESS Virgin

Virgin

S(E), XCR(E) AND XCT(E) ARE ALL ASSUMED TO BE GIVEN IN TABULAR Virgin

FORM WITH LINEAR INTERPOLATION USED BETWEEN TABULATED POINTS. Virgin

IN OTHER WORDS BETWEEN TABULATED POINTS EACH OF THESE THREE IS Virgin

DEFINED BY A FUNCTION OF THE FORM... Virgin

Virgin

F(E)=((E - EK)*FK+1 + (EK+1 - E)*FK)/(EK+1 - EK) Virgin

Virgin

EACH OF THESE THREE CAN BE CONVERTED TO NORMAL FORM BY THE Virgin

CHANGE OF VARIABLES.... Virgin

Virgin

X=(E - 0.5*(EK+1 + EK))/(EK+1 - EK) Virgin

Virgin

IN WHICH CASE X WILL VARY FROM -1 (AT EK) TO +1 (AT EK+1) AND Virgin

EACH FUNCTION REDUCES TO THE NORMAL FORM... Virgin

Virgin

F(X)=0.5*(FK*(1 - X) + FK+1*(1 + X)) Virgin

=0.5*(FK+1 + FK) + 0.5*(FK+1 - FK)*X Virgin

Virgin

BY DEFINING THE AVERAGE VALUE AND 1/2 THE CHANGE ACROSS THE Virgin

INTERVAL. Virgin

Virgin

AVF=0.5*(FK+1 + FK) Virgin

DF= 0.5*(FK+1 - FK) Virgin

DE= 0.5*(EK+1 - EK) Virgin

Virgin

EACH OF THE THREE FUNCTIONS REDUCES TO THE SIMPLE FORM... Virgin

Virgin

F(X)=AVF+DF*X Virgin

Virgin

AND THE TWO REQUIRED INTEGRALS REDUCE TO... Virgin

Virgin

FLUX Virgin

---- Virgin

DE*EXP(-AVXCT*Z) * (INTEGRAL -1 TO +1) Virgin

((AVS+DS*X)*EXP(-DXCT*Z*X)*DX) Virgin

Virgin

REACTION Virgin

-------- Virgin

DE*EXP(-AVXCT*Z) * (INTEGRAL -1 TO +1) Virgin

((AVS*AVXCR+(AVS*DXCR+AVXCR*DS)*X+DS*DXCR*X*X)*EXP(-DXCT*Z*X)*DX) Virgin

Virgin

WHERE Virgin

Virgin

AVXCT = AVERAGE VALUE OF THE TOTAL CROSS SECTION Virgin

AVXCR = AVERAGE VALUE OF THE REACTION CROSS SECTION Virgin

AVS = AVERAGE VALUE OF THE SOURCE Virgin

DXCT = 1/2 THE CHANGE IN THE TOTAL CROSS SECTION Virgin

DXCR = 1/2 THE CHANGE IN THE REACTION CROSS SECTION Virgin

DS = 1/2 THE CHANGE IN THE SOURCE Virgin

DE = 1/2 THE CHANGE IN THE ENERGY Virgin

Virgin

NOTE THAT IN THIS FORM THE ENERGY ONLY APPEARS IN FRONT OF THE Virgin

INTEGRALS AND THE INTEGRALS ARE EXPRESSED ONLY IN TERMS OF THE Virgin

TABULATED VALUES OF S(E), XCT(E) AND XCR(E). IN PARTICULAR NO Virgin

DERIVATIVES ARE USED, SO THAT THERE ARE NO NUMERICAL INSTABILITY Virgin

PROBLEMS IN THE VACINITY OF DISCONTINUITIES IN S(E), XCT(E) OR Virgin

XCR(E). INDEED, SINCE (EK+1 - EK) APPEARS IN FRONT OF THE INTEGRAL Virgin

POINTS OF DISCONTINUITY AUTOMATICALLY MAKE ZERO CONTRIBUTION TO Virgin

THE INTEGRALS. Virgin

Virgin

THE REQUIRED INTEGRALS CAN BE EXPRESSED IN TERMS OF THE THREE Virgin

INTEGRALS IN NORMAL FORM.... Virgin

Virgin

F(A,N) = (INTEGRAL -1 TO 1) (X**N*EXP(-A*X)*DX), N=0,1 AND 2. Virgin

Virgin

THESE THREE INTEGRALS CAN BE EVALUATED TO FIND... Virgin

Virgin

N=0 Virgin

--- Virgin

F(A,0) = (EXP(A)-EXP(-A))/A Virgin

Virgin

N=1 Virgin

--- Virgin

F(A,1) = ((1-A)*EXP(A)-(1+A)*EXP(-A))/(A*A) Virgin

Virgin

N=2 Virgin

--- Virgin

F(A,2) = ((2-2*A+A*A)*EXP(A)-(2+2*A+A*A)*EXP(-A))/(A*A*A) Virgin

Virgin

HOWEVER THESE EXPRESSIONS ARE NUMERICALLY UNSTABLE FOR SMALL Virgin

VALUES OF A. THEREFORE FOR SMALL A THE EXPONENTIAL IN THE Virgin

INTEGRALS ARE EXPANDED IN A POWER SERIES... Virgin

Virgin

EXP(-AX)=1.0-(AX)+(AX)**2/2-(AX)**3/6+(AX)**4/24-........ Virgin

=(SUM K=0 TO INFINITY) (-AX)**K/(K FACTORIAL) Virgin

Virgin

AND THE INTEGRAL REDUCES TO THE FORM.... Virgin

Virgin

(SUM K=0 TO INFINITY) ((-A)**K/(K FACTORIAL)) * Virgin

(INTEGRAL -1 TO 1) (X**(N+K))*DX Virgin

Virgin

WHICH CAN BE ANALYTICALLY EVAULATED TO FIND.... Virgin

(K(N) = K FACTORIAL) Virgin

Virgin

N=0 Virgin

--- Virgin

F(A,0) = 2*(1+(A**2)/K(3)+(A**4)/K(5)+(A**6)/K(7)+.... Virgin

Virgin

N=1 Virgin

--- Virgin

F(A,1) = -2*A*(2/K(3)+4*(A**2)/K(5)+6*(A**4)/K(7)+8*(A**6)/K(9)+.. Virgin

Virgin

N=2 Virgin

--- Virgin

F(A,2) = 2*(2/K(3)+3*4*(A**2)/K(5)+5*6*(A**4)/K(7)+ Virgin

7*8*(A**6)/K(9)+.... Virgin

Virgin

THESE EXPANSIONS ARE USED WHEN THE ABSOLUTE VALUE OF A IS LESS Virgin

THAN 0.1. BY TRUNCATING THE ABOVE SERIES BEFORE A**8 THE ERROR Virgin

RELATIVE TO THE LEADING TERM OF THE SERIES WILL BE 10**(-10), Virgin

YIELDING 10 DIGIT ACCURACY. Virgin

Virgin

AFTER EVALUATING THE ABOVE FUNCTIONS, EITHER DIRECTLY OR BY USING Virgin

THE EXPANSION THE TWO REQUIRED INTEGRALS CAN BE WRITTEN AS... Virgin

Virgin

FLUX Virgin

---- Virgin

DE*EXP(-AVXCT*Z)*(AVS*F(A,0) + DS*F(A,1)) Virgin

Virgin

REACTIONS Virgin

--------- Virgin

DE*EXP(-AVXCT*Z)* Virgin

(AVS*AVXCR*F(A,0) + (AVS*DXCR+AVXCR*DS)*F(A,1) + DS*DXCR*F(A,2)) Virgin

Virgin

INPUT FILES Virgin

----------- Virgin

FILENAME UNIT DESCRIPTION Virgin

-------- ---- ----------- Virgin

INPUT 2 INPUT LINES Virgin

ENDFIN 10 EVALUATED DATA IN ENDF/B FORMAT Virgin

Virgin

OUTPUT FILES Virgin

------------ Virgin

FILENAME UNIT DESCRIPTION Virgin

-------- ---- ----------- Virgin

OUTPUT 3 OUTPUT LISTING Virgin

Virgin

SCRATCH FILES Virgin

------------- Virgin

FILENAME UNIT DESCRIPTION Virgin

-------- ---- ----------- Virgin

SCR1 12 REACTION, FLUX AND CROSS SECTION RESULTS (BCD) Virgin

(SORTED AT END OF RUN AND OUTPUT SEPARATELY) Virgin

SCR2 13 TALLY GROUP ENERGY BOUNDARIES (BINARY) Virgin

SCR3 14 SOURCE SPECTRUM (BINARY) Virgin

SCR4 15 TOTAL CROSS SECTION (BINARY) Virgin

SCR5 16 REACTION CROSS SECTION (BINARY) Virgin

Virgin

OPTIONAL STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILEIO2) Virgin

---------------------------------------------------------------- Virgin

UNIT FILE NAME FORMAT Virgin

---- ---------- ------ Virgin

2 VIRGIN.INP BCD Virgin

3 VIRGIN.LST BCD Virgin

10 ENDFB.IN BCD Virgin

11-15 (SCRATCH) BINARY Virgin

16 PLOTTAB.CUR PLOTTAB OUTPUT FORMAT DATA Virgin

Virgin

INPUT LINES Virgin

----------- Virgin

ANY NUMBER OF CASES MAY BE RUN ONE AFTER THE OTHER. AFTER THE Virgin

FIRST CASE HAS BEEN RUN THE FOLLOWING CASES MAY USE THE SAME Virgin

THICKNESSES, GROUP STRUCTURE AND SPECTRUM AS THE PRECEDING CASE. Virgin

IN ADDITION THE TRANSMITTED SPECTRUM FROM ONE CASE MAY BE USED Virgin

AS THE INCIDENT SPECTRUM IN THE NEXT CASE, TO ALLOW MULTIPLE Virgin

LAYERS OF DIFFERENT MATERIALS. Virgin

Virgin

LINE COLS. FORMAT DESCRIPTION Virgin

---- ----- ------ ---------- Virgin

1 1-60 ENDF/B INPUT DATA FILENAME Virgin

(STANDARD OPTION = ENDFB.IN) Virgin

Virgin

LEAVE THE DEFINITION OF THE FILENAMES BLANK - THE PROGRAM WILL Virgin

THEN USE STANDARD FILENAMES. Virgin

Virgin

2-3 1-72 18A4 TWO LINE TITLE DESCRIBING PROBLEM Virgin

4 1- 6 I6 ZA (1000*Z+A) OF TARGET FOR TOTAL Virgin

7-11 I5 MT OF TOTAL Virgin

12-22 E11.4 DENSITY FOR TOTAL Virgin

23-28 I6 ZA (1000*Z+A) OF TARGET FOR REACTION Virgin

29-33 I5 MT OF REACTION Virgin

= 0 - NO REACTION CALCULATION (ONLY FLUX). Virgin

= GREATER THAN 0 - CALCULATE REACTIONS. Virgin

34-44 E11.4 DENSITY FOR REACTION Virgin

45-50 I6 NUMBER OF TARGET THICKNESSES Virgin

= GREATER THAN 0 = READ FROM INPUT Virgin

(1 TO 2000 ALLOWED) Virgin

= 0 = SAME AS LAST CASE Virgin

51-55 I5 NUMBER OF TALLY GROUPS Virgin

(REMEMBER NUMBER OF GROUP BOUNDARIES Virgin

IS ONE MORE THAN THE NUMBER OF GROUPS) Virgin

UP TO 2000 GROUPS ARE ALLOWED Virgin

BUILT-IN GROUP STRUCTURES. Virgin

= GREATER THAN 0 = READ FROM INPUT Virgin

= 0 SAME AS LAST CASE Virgin

= -1 TART 175 GROUPS Virgin

= -2 ORNL 50 GROUPS Virgin

= -3 ORNL 126 GROUPS Virgin

= -4 ORNL 171 GROUPS Virgin

= -5 SAND-II 620 GROUPS..UP TO 18 MEV. Virgin

= -6 SAND-II 640 GROUPS..UP TO 20 MEV. Virgin

= -7 WIMS 69 GROUPS Virgin

= -8 GAM-I 68 GROUPS Virgin

= -9 GAM-II 99 GROUPS Virgin

=-10 MUFT 54 GROUPS Virgin

=-11 ABBN 28 GROUPS Virgin

56-60 I5 NUMBER OF POINTS IN SOURCE SPECTRUM Virgin

(MUST BE AT LEAST TWO POINTS) Virgin

= GREATER THAN 1 = READ FROM INPUT Virgin

= 0 = SAME AS LAST CASE Virgin

= -1 = CONSTANT (ENERGY INDEPENDENT) Virgin

= -2 = 1/E Virgin

= -3 = BLACKBODY - PHOTON SPECTRUM Virgin

= -4 = BLACKBODY - ENERGY SPECTRUM Virgin

= -5 = TRANSMITTED SPECTRUM FROM LAST CASE Virgin

NOTE, ALL SPECTRA, EXCEPT THE TRANSMITTED Virgin

SPECTRUM FROM THE LAST CASE, WILL BE Virgin

NORMALIZED SUCH THAT ITS INTEGRAL OVER Virgin

ENERGY WILL BE UNITY. Virgin

61-64 1X,3I1 SPATIALLY DEPENDENT OUTOUT Virgin

= 0 = NO Virgin

= 1 = YES Virgin

FOR THE 3 QUANTITIES Virgin

COLUMN 67 FLUX Virgin

68 REACTIONS Virgin

69 AVERAGE CROSS SECTION Virgin

65-65 I1 ENERGY DEPENDENT OUTOUT Virgin

= 0 = NONE Virgin

= 1 = INCIDENT SPECTRUM Virgin

= 2 = TRANSMITTED SPECTRUM Virgin

= 3 = INCIDENT REACTIONS Virgin

= 4 = TRANSMIITED REACTIONS Virgin

= 5 = TOTAL CROSS SECTION Virgin

= 6 = REACTION CROSS SECTION Virgin

5 1-11 E11.4 BLACKBODY TEMPERATURE IN EV Virgin

12-22 E11.4 FLUX NORMALIZATION Virgin

23-33 E11.4 REACTION NORMALIZATION Virgin

CALCULATIONS WILL BE BASED ON THE SPECTRUM Virgin

AND CROSS SECTIONS AS READ. AT OUTPUT THE Virgin

RESULTS WILL BE MULTIPLIED BY THESE Virgin

NORMALIZATION FACTORS. Virgin

34-44 I11 DENSITY PROFILE Virgin

= 0 - UNIFORM - BASED ON TOTAL DENSITY Virgin

= 1 - UNIFORM - TOTAL + REACTION DENSITY Virgin

= 2 - TOTAL + LINEAR REACTION Virgin

= 3 - LINEAR (TOTAL + REACTION) Virgin

= 4 - TOTAL + SQUARE REACTION Virgin

= 5 - SQUARE (TOTAL + REACTION) Virgin

= 6 - TOTAL + CUBIC REACTION Virgin

= 7 - CUBIC (TOTAL + REACTION) Virgin

6-N 1-66 6E11.4 TARGET THICKNESSES IN CM Virgin

IF SAME AS LAST CASE THIS SECTION IS NOT Virgin

INCLUDED IN THE INPUT. Virgin

VARY 1-66 6E11.4 TALLY GROUP ENERGY BOUNDARIES Virgin

(NUMBER OF BOUNDARIES IS ONE MORE THAN Virgin

THE NUMBER OF TALLY GROUPS) Virgin

IF THE STANDARD OPTION (-11 TO 0) IS Virgin

SELECTED THIS SECTION IS NOT INCLUDED Virgin

IN THE INPUT Virgin

VARY 1-66 6E11.4 SOURCE SPECTRUM IN ENERGY (EV)-SOURCE PAIRS Virgin

(MUST BE AT LEAST TWO POINTS) Virgin

IF STANDARD OPTION (-5 TO 0) IS SELECTED THIS Virgin

SECTION IS NOT INCLUDED IN THE INPUT Virgin

Virgin

ANY NUMBER OF CASES MAY BE RUN ONE AFTER ANOTHER. Virgin

Virgin

EXAMPLE INPUT NO. 1 Virgin

------------------- Virgin

CALCULATE THE UNCOLLIDED FLUX AND CAPTURE (MT=102) THROUGH Virgin

30 CM OF IRON (DENSITY 7.87 G/CC). TALLY THE RESULTS USING Virgin

THE TART 175 GROUP STRUCTURE. THE SOURCE WILL BE CONSTANT Virgin

FROM 1 KEV TO 20 MEV. USE THE STANDARD ENDF/B INPUT DATA Virgin

FILENAME. Virgin

Virgin

ENDFB.IN Virgin

IRON 0 TO 30 CM THICK. Virgin

CONSTANT SOURCE FROM 1 KEV TO 20 MEV. Virgin

26000 1 7.87000+ 0 26000 102 7.87000+ 0 2 0 2 1100 Virgin

0.00000+ 0 1.00000+ 0 1.00000+ 0 0 0.00000+00 Virgin

0.00000+00 3.00000+01 Virgin

1.0000E+03 1.0000E+00 2.0000E+07 1.0000E+00 Virgin

Virgin

EXAMPLE INPUT NO. 2 Virgin

------------------- Virgin

CALCULATE THE UNCOLLIDED PHOTON FLUX THROUGH A MIXTURE OF SILICON Virgin

AND IRON FOR 100 MEV PHOTONS INCIDENT. THE TRANSMISSION WILL BE Virgin

CALCULATED FOR 21 THICKNESSES VARYING BETWEEN 0 AND 1 CM. THERE Virgin

WILL BE ONLY 1 TALLY GROUP SPANNING A VERY NARROW ENERGY RANGE Virgin

NEAR 100 MEV, AND THE SOURCE SPECTRUM WILL BE CONSTANT OVER THE Virgin

SAME ENERGY RANGE. USE THE STANDARD ENDF/B INPUT DATA FILENAME Virgin

BY LEAVING THE FIRST INPUT LINE BLANK. Virgin

Virgin

(THIS IS A BLANK LINE TO USE THE STANDARD INPUT FILENAME) Virgin

100 MEV PHOTONS Virgin

SILICON + 5 % IRON Virgin

14000 521 2.30000+ 0 26000 521 1.15000- 1 21 1 2 1000 Virgin

0.00000+ 0 1.00000+ 0 1.00000+ 0 1 0.00000+00 Virgin

0.00000+00 5.00000-01 1.00000+00 1.50000+00 2.00000+00 2.50000+00 Virgin

3.00000+00 3.50000+00 4.00000+00 4.50000+00 5.00000+00 5.50000+00 Virgin

6.00000+00 6.50000+00 7.00000+00 7.50000+00 8.00000+00 8.50000+00 Virgin

9.00000+00 9.50000+00 1.00000+01 Virgin

9.99000+ 7 1.00100+ 8 Virgin

9.99000+ 7 1.00000+ 4 1.00100+ 8 1.00000+ 4 Virgin

Virgin

======================================================================= Virgin