last modified: 27-NOV-2001 | catalog | categories | new | search |

IAEA0964 ZZ-FGXRRS.

ZZ FGXRRS, 10 Neutron-Group, 7 Gamma-Group Self-Shielded Cross-Section in ANISN Format

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-FGXRRS.
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2. COMPUTERS
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Program name Package id Status Status date
ZZ-FGXRRS IAEA0964/01 Arrived 27-NOV-2001

Machines used:

Package ID Orig. computer Test computer
IAEA0964/01 CDC CYBER 172
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3. DESCRIPTION OF PROGRAM OR FUNCTION


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  FORMAT: ANISN

  NUMBER OF GROUPS: 10 neutron, 7 gamma-ray

NUCLIDES: 78 materials (mixture components) Flux trap, Core, Zircaloy-4, D2O, H2O, SS-304, Air, Boral, Lead, B4C+Epoxy, Steel, Magnetite, Ordinary concrete, Limonite, Bor induced high density concrete.

  ORIGIN: VITAMIN-C fine-group cross section library

WEIGHTING SPECTRUM: weighting functions representative of a 20% enriched uranium fueled, D2O reflected and pool type research reactor.

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Starting with the DLC-41C/VITAMIN-C fine-group cross section library, a composition-dependent coupled few-group (10n,7g) self-shielded microscopic ANISN-formatted cross section library was  generated to be used for research reactor shielding calculations. FGXRRS was generated by collapsing DLC-41C/VITAMIN-C using the spectra of the zone-dependent total fluxes.
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4. METHOD OF SOLUTION

The data were collapsed from a fine-group structure using the weighting functions representative of a 20% enriched uranium fueled, D2O reflected and pool type research reactor. Thus the application of this data for problems not similar  to this type of problem should be done with caution.
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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

The basic cross section source data for the generation of the FGXRRS cross section library was DLC-41C/VITAMIN-C neutron, secondary gamma-ray production, and gamma-ray interaction cross section library in AMPX master interface format. PSR-63/AMPX-II modules were used to prepare FGXRRS, which includes 78 materials. The Legendre order of expansion for angular distribution is 3.
   GITAPE: Group Independent TAPE processing.
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9. STATUS
Package ID Status date Status
IAEA0964/01 27-NOV-2001 Masterfiled Arrived
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10. REFERENCES:
IAEA0964/01, included references:
- Jung-Do Kim et al.:
  FGXRRS: A Few-Group Cross Section Library for Research Reactor
  Shielding Calculations.
  KAERI/TR-110/87  (August 21, 1987)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0964/01 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 AUTHORS

          Korea Advanced Energy Research Institute
           Daeduk-Danji
           Choongham, Korea
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16. MATERIAL AVAILABLE
IAEA0964/01
symb data lib    mag tapeFGXRRS library, 10-N, 7 G-Ray ANISN format LBSTP
source program   mag tapeGITAPE source fortran                      SRCTP
test-case data   mag tapeJCL and sample input for GITAPE            DATTP
test-case data   mag tapeJCL and sample input for ANISN             DATTP
test-case output mag tapeANISN sample output                        OUTTP
report                   KAERI/TR-110/87  (August 21, 1987)         REPPT
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • Z. Data.

Keywords: ENDF/B, coupled neutron gamma cross sections, cross sections, data library, multigroup, self-shielding, shielding.