1. NAME AND TITLE
GERES: A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous
Fast Reactor Cell Calculations Using MC2II Data
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
7. TYPICAL RUNNING TIME
A typical run with 156 groups, 13 isotopes, in cylindrical geometry, requires 1 m on a IBM
8. COMPUTER HARDWARE REQUIREMENTS
9. COMPUTER SOFTWARE REQUIREMENTS
IBM Fortran IV, ASSEMBLER (Timing routines), MVS Operating System.
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
KEYWORDS: NEUTRON CROSS SECTION PROCESSING; REACTOR PHYSICS