IAEA0964 ZZ-FGXRRS.
ZZ FGXRRS, 10 Neutron-Group, 7 Gamma-Group Self-Shielded Cross-Section in ANISN Format
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
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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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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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
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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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.
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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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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IAEA0964/01
symb data lib mag tapeFGXRRS library, 10-N, 7 G-Ray ANISN format LBSTPsource 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
Keywords: ENDF/B, coupled neutron gamma cross sections, cross sections, data library, multigroup, self-shielding, shielding.