1. NAME AND TITLE

SLAROM: A Code to Produce Cell Averaged Cross Sections for Fast Critical Assemblies and Fast Power Reactors

2. CONTRIBUTOR

Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, Japan.

3. CODING LANGUAGE AND COMPUTER

Fortran 77 and Assembler; FACOM M380.

4. NATURE OF PROBLEM SOLVED

SLAROM solves the neutron integral transport equations to determine the flux distribution and spectra in a fast reactor lattice and calculates cell averaged effective cross sections. The code uses multigroup data of the type in DLC-111/JFS that use Bondarenko factors for resonance effects.

5. METHOD OF SOLUTION

SLAROM consists of six blocks: PREP, PATH, PIJF, EDIT, RATE, and EIND. PREP calculates region dependent effective or homogenized multigroup cross sections, PATH calculates the collision probability, and PIJF solves the multigroup integral transport equations by the matrix inversion method. Cell averaged cross sections and diffusion coefficients and calculated using EDIT, in-cell reaction rate distributions are calculated with RATE, and collapsed cross sections are produced by one-dimensional diffusion calculations with EIND.

6. RESTRICTIONS OR LIMITATIONS

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

7. TYPICAL RUNNING TIME

An infinite plate geometry problem with 14 regions requires about 30 s on a FACOM M380.

8. COMPUTER HARDWARE REQUIREMENTS

FACOM M380 with partitioned data sets to store intermediate cross sections.

9. COMPUTER SOFTWARE REQUIREMENTS

Fortran 77, Assembler, FACOM OS IV Operating System.

10. REFERENCE

M. Nakagawa and K. Tsuchihashi, "SLAROM - A Code for Cell Homogenization Calculation of Fast Reactor," JAERI 1294 (September 1984).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and two (1.2MB) DOS diskettes which contain the source code, sample problem input and output, data library and conversion program.

12. DATE OF ABSTRACT

June 1987.