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

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

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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 3.0x104 eV   -> spectrum from MC2 "ultrafine" multigroup calculations + resonances

from 3.0x104 eV to 3.0x106    -> spectrum from MC2 "fine" multigroup calculations + resonances

from 3.0x106 eV to 1.0x17 eV  -> shape of a fission spectrum

from 1.0x107 eV to 1.257x107  -> 1/E

from 1.257x107 to 1.557x107   -> velocity exponential fusion peak

from 1.557x107 to 2x107 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 105 eV to 0.625 eV     -> mid-life PWR thermal spectrum

from 0.625 eV to 3.x104 eV  -> spectrum from MC2 "ultrafine"  multigroup calculations + resonances

from 3.x104 eV to 3.x106    -> spectrum from MC2 "fine" multigroup calculations + resonances

from 3.x106 eV to 107 eV    -> shape of a fission spectrum

from 107 eV to 1.257x107    -> 1/E

from 1.257x107 to 1.557x107 -> velocity exponential fusion peak

from 1.557x107 to 2x107eV   -> 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. METHODS

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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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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8. RELATED OR 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: "MC2, 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, T.R. England, R.J. LaBauve and R.M. Boicourt:
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. HARDWARE REQUIREMENTS

To run the test cases of TOAFEW-V included in the package, main storage requirements are as follows:

 

CYBER 740

words (octal)

VAX-11/780

bytes

Test case

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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15. NAME AND ESTABLISHMENT OF AUTHORS

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
TOAFEW-V Fortran source file
LAPFX-V data library (unit 1)
input and output from TOAFEW-V
documentation
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
  • Z. Data

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