=======================================================================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 VERS. 2023-1 (Feb. 2023) *Decreased page siZe from 600,000 SIXPAK to 120,000 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