Computer Programs
DLC-0054 ZZ-LAFPX-E.
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DLC-0054 ZZ-LAFPX-E.

ZZ LAFPX-V, Multigroup Fission Product Data Library from ENDF/B-V by Program NJOY

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-LAFPX-E.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-LAFPX-E DLC-0054/01 Tested 18-JAN-1985
ZZ-LAFPX-E DLC-0054/02 Arrived 23-JAN-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0054/01 CDC 7600 Many Computers
DLC-0054/02 CDC 1604
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3. DESCRIPTION OF PROGRAM OR FUNCTION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  LAFPX-IV
  ========

  FORMAT:

  NUMBER OF GROUPS: 154-group fission-product cross sections.

NUCLIDES: Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er.

  ORIGIN: ENDF/B-IV

  WEIGHTING SPECTRUM:
from 10**5 eV to 0.625 eV    -> mid-life PWR thermal spectrum
from 0.625 eV to 3.*10**4 eV -> spectrum from MC**2 "ultrafine"
multigroup calculations + resonances from 3.*10**4 eV to 3.*10**6 -> spectrum from MC**2 "fine"
multigroup calculations + resonances from 3.*10**6 eV to 10**7 eV -> shape of a fission spectrum
from 10**7 eV to 1.257*10**7 -> 1/E
from 1.257*10**7 to 1.557*10**7 -> velocity exponential fusion peak
from 1.557*10**7 to 2*10**7  eV -> 1/E


  LAFPX-IV
  ========

  FORMAT:

  NUMBER OF GROUPS: 154-group fission-product cross sections.

NUCLIDES: Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er; Th, Pa U, Np, Pu, Am, Cm, Bk, Cf, Es.

  ORIGIN: ENDF/B-V

  WEIGHTING SPECTRUM:
from 10**5 eV to 0.625 eV    -> mid-life PWR thermal spectrum
from 0.625 eV to 3.*10**4 eV -> spectrum from MC**2 "ultrafine"
multigroup calculations + resonances from 3.*10**4 eV to 3.*10**6 -> spectrum from MC**2 "fine"
multigroup calculations + resonances from 3.*10**6 eV to 10**7 eV -> shape of a fission spectrum
from 10**7 eV to 1.257*10**7 -> 1/E
from 1.257*10**7 to 1.557*10**7 -> velocity exponential fusion peak  from 1.557*10**7 to 2*10**7  eV -> 1/E

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
LAFPX-V is a data library of 154-group fission-product cross sections processed from ENDFB-V with a typical light-water reactor flux spectrum and temperature.
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4. METHOD OF SOLUTION

The library has been generated from the 181 nuclides of the 824 nuclide ENDF/B fission product library using the code NJOY (PSR-0171).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

The cross-section collapsing program TOAFEW-V has been run by NEA-DB on both CDC CYBER 740 and VAX-11/780. Execution times for the test cases were: 200 CPU seconds for cases 1 and 2; 333 CPU seconds for case 3.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
DLC-0054/01
TOAFEW-V Multigroup X-Section Collapsing Code ---------* 1-DX
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9. STATUS
Package ID Status date Status
DLC-0054/01 18-JAN-1985 Tested at NEADB
DLC-0054/02 23-JAN-2002 Masterfiled Arrived
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10. REFERENCES

- T.R. England and R.E. Schenter:
  "ENDF/B-IV Fission-Product Files: Summary of Major Nuclear Data"
  LA-6116-MS (ENDF-223) (October 1975)
- R.E. MacFarlaine and R.M. Boicourt:
  "NJOY - A Neutron and Photon Cross-Section Processing Code"
  Trans. Am. Nucl. Soc. 22, 720 (1975)
- R.J. LaBauve, C.R. Weisbin, R.E. Seamon, M.E. Battat, D.R. Harris,   P.G. Young and M.M. Klein:
  "PENDF: A Library of Nuclear Data for Monte Carlo Calculations
   Derived from Data in the ENDF/B Format"
  LA-5687 (October 1974)
- B.J. Toppel, A.L. Rago and D.M. O'Shea:
  "MC**2, a Code to Calculate Multigroup Cross Sections"
  ANL-7318 (1967)
- R.J. LaBauve and W.B. Wilson:
"Proposal to Extend CSEWG Neutron and Photon Multigroup Structures     for Wider Applications"
  LA-6240-P (February 1976)
DLC-0054/01, included references:
- W.B. Wilson, T.R. England, R.J. LaBauve:
  Multigroup and Few-Group Cross Sections for ENDF/B-IV Fission
  Products; The TOAFEW Collapsing Code and Data File of 154-Group
  Fission-Product Cross Sections. LA-7174-MS  (March 1978)
DLC-0054/02, included references:
- W.B. Wilson et al.:
  TOAFEW-V Multigroup Cross-Section Collapsin Code and Library of
  154-Group-Processed ENDF/B/V Fission-Product and Actinide Cross
  Sections
  NP-2345 (April 1982).
- W.B. Wilson, T.R. England and R.J. LaBauve;
"Multigroup and Few-Group Cross Sections for ENDF/B-IV Fission
Products; The TOAFEW Collapsing Code and Data File of 154-Group
Fission-Product Cross Sections"
LA-7174-MS (March 1978)
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11. MACHINE REQUIREMENTS

To run the test cases of TOAFEW-V included in the package, main storage requirements are as follows:
            CYBER 740     VAX-11/780      Test case
          words (octal)      bytes
          -------------   ------------    ---------
             42,700          29,000        1, 2, 3
             66,700          70,000        4
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0054/01 FORTRAN-IV
DLC-0054/02 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Theoretical Division, Los Alamos Scientific Laboratory, Los Alamos, New Mexico, for the Electric Power Research Institute, Palo Alto, California, and the United States Nuclear Regulatory Commission, Washington, D.C.
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16. MATERIAL AVAILABLE
DLC-0054/02
source program   mag tapeTOAFEW-V Fortran source file               SRCTP
symb data lib    mag tapeLAPFX-V data library (unit 1)              LBSTP
test-case data   mag tapeinput and output from TOAFEW-V             DATTP
report                   NP-2345 (April 1982)                       REPPT
DLC-0054/01
File name File description Records
DLC0054_01.003 ZZ-LAFPX-V INFORMATION FILE 55
DLC0054_01.004 ZZ-LAFPX-V DATA LIBRARY (FORMATTED) 202326
DLC0054_01.005 TOAFEW-V SOURCE PROGRAM (FORTRAN CDC) 1008
DLC0054_01.006 TOAFEW-V (CDC) TEST CASE INP./OUTP. 715
DLC0054_01.007 TOAFEW-V SOURCE PROGRAM (VAX-11/780) 1026
DLC0054_01.008 TOAFEW-V (VAX-11/780) TEST CASE INP./OUTP. 703
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17. CATEGORIES
  • C. Static Design Studies
  • Z. Data.

Keywords: BWR reactors, cross sections, data library, fission products, multigroup.