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RSIC CODE PACKAGE PSR-241


1. NAME AND TITLE

GERES: A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous Fast Reactor Cell Calculations Using MC2II Data

2. CONTRIBUTOR

ENEA Departimento Technologie Intersettoriali di Base, Centro Ricerche Energia "Ezio Clementel," Bologna, Italy.

3. CODING LANGUAGE AND COMPUTER

Fortran IV; IBM 370.

4. NATURE OF PROBLEM SOLVED

GERES performs fast reactor cell calculations, producing a multigroup cross-section set for each zone of a heterogeneous cell, for subsequent use in the CCC-254/ANISN discrete ordinates code. Multiple slabs or two-region cylindrical cells can be treated.

5. METHOD OF SOLUTION

Resonance contributions to the cross section are computed for each zone and are added to cross sections that do not include the resonance contribution. GERES uses data produced by MC2II, performs the necessary combinations and calculations, and produces libraries for use in ANISN.

6. RESTRICTIONS OR LIMITATIONS

Variable dimensioning removes most restrictions on the complexity of the problems that can be treated.

7. TYPICAL RUNNING TIME

A typical run with 156 groups, 13 isotopes, in cylindrical geometry, requires 1 m on a IBM 370/168.

8. COMPUTER HARDWARE REQUIREMENTS

IBM 370.

9. COMPUTER SOFTWARE REQUIREMENTS

IBM Fortran IV, ASSEMBLER (Timing routines), MVS Operating System.

10. REFERENCE

M. Galli, "GERES - A Code to Process MC2 Data for Heterogeneous Fast Reactor Cell Calculations," RT/TIB/85/26, (September 1985).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source code, sample problem input and output, a variety of unformatted libraries produced by MC2.

12. DATE OF ABSTRACT

February 1987.

KEYWORDS: NEUTRON CROSS SECTION PROCESSING; REACTOR PHYSICS