1. NAME AND TITLE OF DATA LIBRARY
FGXXRS: Few Group Cross Section Library for Research Reactor Calculations
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
GITAPE: Group Independent TAPE processing.
Korea Advanced Energy Research Institute, Daeduk-Danji, Choongham, Korea.
4. HISTORICAL BACKGROUND AND INFORMATION
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.
5. APPLICATION OF THE DATA
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.
6. SOURCE AND SCOPE OF DATA
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
FGXRSS, which includes 78 materials. The Legendre order of expansion for angular distribution is
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
GITAPE selects elements to be used in a problem and prepares a group-independent cross section
library tape for ANISN. Sample case input and output for running ANISN is included in the package.
8. DATA FORMAT AND COMPUTER
Card images; CDC CYBER.
9. TYPICAL RUNNING TIME
Jung-Do Kim, Kab-Soo Chung, Byung-Chul Lee, Eun-Hee Kim, and Ji-Bok Lee, "FGXXRS: A
Few-Group Cross Section Library for Research Reactor Shielding Calculations," KAERI/TR-110/87
11. CONTENTS OF LIBRARY
Included are the referenced document and one (1.2MB) DOS diskette.
12. DATE OF ABSTRACT
KEYWORD: ANISN FORMAT; COUPLED NEUTRON-GAMMAY-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B