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DLC-0089 ZZ-LUMP.

ZZ LUMP, Lumped Fission Product Cross-Section Library for Fast Reactor Analysis from ENDF/B-V

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-LUMP.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-LUMP DLC-0089/01 Arrived 05-FEB-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0089/01 IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION


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  FORMAT: ENDF/B format

  NUMBER OF GROUPS: 171 group libraries

NUCLIDES: Zn, Ga, Ge, As, Se, Br, Kr, Sr, Y, Zr, Tc, Pd, Ag, Cd, Sn, Sb, Te, I, Xe, Pr, Gd, Tb, U, Pu, O, Na, Fe, Ni, Cr, Mo, Mn.

  ORIGIN: ENDF/B-V

  WEIGHTING SPECTRUM: yes

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Evaluated Lumped Fission Product Cross Sections for Fast Reactor Analysis - Based on ENDF/B-V Data. Both one-lump and two-lump models have been investigated in detail. Fission product inventories at various burnup steps were calculated by the EPRI-CINDER-2 code and used as weighting functions for lumping.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
DLC-0089/01 05-FEB-2002 Masterfiled Arrived
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10. REFERENCES:
DLC-0089/01, included references:
- J.R. Liaw and H. Henryson II:
  Evaluation of Lumped Fission Product Cross Sections for Fast
  Reactor Analysis - An Update. Intra-Laboratory Memo (May 1981)
- J.R. Liaw and H. Henryson II:
  Evaluation of Lumped Fission Product Cross Sections for Fast
  Reactor Analysis.  FRA-TM-134  (February 1981)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0089/01 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

J.R. Liaw and H. Henryson II
Applied Physics Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439
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16. MATERIAL AVAILABLE
DLC-0089/01
test-case data   mag tapeSample Problem and JCL                     DATTP
source program   mag tapeMERGER Source                              SRCTP
symb data lib    mag tapeLUMP Cross Section Data                    LBSTP
symb data lib    mag tapeLUMP Merged Cross Section                  LBSTP
test-case output mag tapeLUMP                                       OUTTP
report                   Intra-Laboratory Memo (May 1981)           REPPT
report                   FRA-TM-134  (February 1981)                REPPT
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • Z. Data.

Keywords: ENDF/B, LMFBR reactors, data, fast reactors, fission products.