=======================================================================
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
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
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
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
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
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
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
=
(SQRT(EP(CM)) - SQRT(E(MM)))**2 FOR
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
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