=======================================================================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 CHANGESIXPAK
*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 PARTICLESIXPAK
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
VERS. 2007-1 (JAN. 2007) *CHECKED AGAINST ALL ENDF/B-VII. SIXPAK
*INCREASED MAXIMUM TABLE SIZE FROM SIXPAK
12,000 TO 120,000. SIXPAK
VERS. 2007-2 (DEC. 2007) *72 CHARACTER FILE NAMES. SIXPAK
VERS. 2010-1 (Apr. 2010) *General update based on user feedbackSIXPAK
VERS. 2011-1 (May 2011) *Added MF/MT=9/5 yield output startingSIXPAK
from MF/MT=6/5 distributions. SIXPAK
*Increased maximum Legendre order fromSIXPAK
30 to 1,000 - WARNING - using more SIXPAK
than 30 results in NONSENSE = NOISE!!SIXPAK
VERS. 2012-1 (Oct. 2012) *Increased max. point count to 500,000SIXPAK
*Added CODENAME SIXPAK
*32 and 64 bit Compatible SIXPAK
*Added ERROR stop SIXPAK
*For photons, combine discrete and SIXPAK
continuum into tabulated increasing SIXPAK
energy order. SIXPAK
*Check energy output order increasing.SIXPAK
Print WARNING if not increasing - do SIXPAK
not STOP- stopping would prevent ALL SIXPAK
output - the user may not be at all SIXPAK
interested in the BAD data, but may SIXPAK
be interested in other output data SIXPAK
that is o.k. SIXPAK
VERS. 2015-1 (Jan. 2015) *Extended OUT9. SIXPAK
*Replaced ALL 3 way IF Statements. SIXPAK
*Deleted unused coding. SIXPAK
VERS. 2017-1 (May 2017) *Increased max. point to 600,000 SIXPAK
*Updated based on user feedback SIXPAK
VERS. 2017-2 (Oct. 2017) *Updated for new P(nu) formats = SIXPAK
Recognized and ignored = no MF=5 SIXPAK
equivalent. SIXPAK
VERS. 2018-1 (Jan. 2018) *Updated to skip Nu-Bar Data = there SIXPAK
is no double-differential data to SIXPAK
process. SIXPAK
*On-linr report for ALL ENDERROR SIXPAK
VERS. 2019-1 (June 2019) *Additional Interpolation Law Tests SIXPAK
*Checked Maximum Tabulated Energy to SIXPAK
insure it is the same for all MTs - SIXPAK
if not, print WARNING messages. SIXPAK
*WARNING MT=5 - not allowed in MF=4/5 SIXPAK
see ENDF102 - but will translate hereSIXPAK
to allow diagnostic use ONLY. SIXPAK
*Corrected END Histogram - guarantee SIXPAK
it ends with zero cross section,e.g.,SIXPAK
(E,Y) only defines upper energy of SIXPAK
the last group - Y has no meaning, SIXPAK
by ENDF convention it should be Y = 0SIXPAK
VERS. 2020-1 (Mar. 2020) *Added ENDFB.MF3 for MF/MT=3/5 parta SIXPAK
based on MF=6/5. SIXPAK
*Added Target Isomer State SIXPAK
VERS. 2021-1 (Jan. 2021) *Updated for FORTRAN 2018 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
SIXPAK
PRESENT CONTACT INFORMATION SIXPAK
--------------------------- SIXPAK
Dermott E. Cullen SIXPAK
1466 Hudson Way SIXPAK
Livermore, CA 94550 SIXPAK
U.S.A. SIXPAK
Telephone 925-443-1911 SIXPAK
E. Mail RedCullen1@Comcast.net SIXPAK
Website RedCullen1.net/HOMEPAGE.NEW 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 COMPUTERSIXPAK
INDEPENDENT PROGRAMS THAT CAN EASILY BE IMPLEMENTED ON ANY ONE SIXPAK
OF A WIDE VARIETY OF COMPUTERS. IN ORDER TO ASSIST IN THIS PROJECTSIXPAK
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 15SIXPAK
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 COSSIXPAK
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
6 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
6) ENDFB.MF3 - TABULATED Charged Particle Cross Section for MT=5 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 SUCHSIXPAK
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 ENERGYSIXPAK
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 DATASIXPAK
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 SCATTERINGSIXPAK
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
19 ENDFB.MT9 SIXPAK
20 ENDFB.MT3 SIXPAK
15 PLOTTAB.INP SIXPAK
16 PLOTTAB.CUR SIXPAK
SIXPAK
SIXPAK
INPUT PARAMETERS SIXPAK
==================================================================SIXPAK
LINE COLS. DESCRIPTION SIXPAK
---- ----- ----------- SIXPAK
1 1-72 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 EXPLICITLYSIXPAK
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