1. NAME AND TITLE OF DATA LIBRARY

GARG: 27-Group Neutron Cross Sections in Discrete Ordinates Format Generated with FIGERO (PSR-149) from ENDF-B Data.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

REAR

3. CONTRIBUTOR

Experimental Reactor Physics Section, Bhabha Atomic Research Center, Bombay, India.

4. HISTORICAL BACKGROUND AND INFORMATION

GARG is a 27-group neutron cross section set in discrete ordinates format generated with PSR-149/FIGERO from ENDF/B data.

5. APPLICATION OF THE DATA

GARG contains four files. File 1 (RESEND code) can process the ENDF/B resonance data. File 2 (INSCAT code) calculates the group-to-group scattering matrices for the discrete and continuum inelastic data and (n,2n) reaction data. File 3 (FIGERO code) calculates multigroup cross-sections using the basic data from the ENDF/B library. File 4 contains a 27-group cross-section library and the self-shielding factors for several elements.

6. SOURCE AND SCOPE OF DATA

The package contains cross sections in DTF-IV format for 16 elements:

⁶Li, ⁷Li, ⁹Be, ²³²Th, ²⁴¹Pu, ¹⁶O, ²³⁵U, ¹²C, ²³³U, ²³⁹Pu, ²⁴⁰Pu, ²³⁸U, ⁵²Cr, ⁵⁸Ni, ²³Na, ⁵⁶Fe.

Also included are self-shield factors, cross sections and inelastic matrices in 1-DX format for 11 elements:

Cr, Ni, Fe, ²³⁵U, ²³⁸U, ²³⁹Pu, ²⁴⁰Pu, Na, ¹⁶O, ¹²C, and ²⁴¹Pu.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

REAR, containing 53 logical records, is written in Fortran IV.

8. DATA FORMAT AND COMPUTER

BCD output; CDC.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCE

S. B. Garg, "GARG, A 27-Group Neutron Cross Section Library in Discrete Ordinates Format Generated with FIGERO (PSR-149) from ENDF-B Data."

11. CONTENTS OF LIBRARY

Included are the referenced document and one (1.2MB) DOS diskette which contains the cross sections in DTF-IF format, the self-shield factors, cross sections, and inelastic matrices in IDX format, and the retrieval program written in Fortran IV.

12. DATE OF ABSTRACT

March 1985, updated January 1992.