DLC-0054 ZZ-LAFPX-E.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-LAFPX-E.

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

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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.

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).

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:

TOAFEW-V Multigroup X-Section Collapsing Code ---------* 1-DX

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)

- 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)
- 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)

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

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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.

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

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