RSICC CODE PACKAGE CCC-716

1. NAME AND TITLE

SRAC95: Thermal Reactor Code System for Reactor Design and Analysis.

AUXILIARY PROGRAM

ASMBURN: Auxiliary code for fuel assembly burn-up calculation

COREBN: Auxiliary code for core burn-up calculation.

2. CONTRIBUTORS

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

3. CODING LANGUAGE AND COMPUTER

Fortran 77 and C; Sun, IBM, HP, Facom, & Linux PC (C00716MNYWS00).

4. NATURE OF PROBLEM SOLVED

SRAC95 is a general purpose neutronics code system applicable to core analyses of various types of reactors, including cell calculation with burn up, core calculation for any type of thermal reactor; where core burn up calculation and fuel management were done by an auxiliary code. Since the publication of JAERI-1302 for the revised SRAC in 1986, a number of additions and modifications were made for nuclear data libraries and programs. In this version, many new functions and data are implemented to support nuclear design studies of advanced reactors. SRAC95 can be used for burnup credit analysis within the ORIGEN2 and SWAT (CCC-714) code system.

5. METHOD OF SOLUTION

Collision probability method, 1D and 2D Sn for cell calculations; 1D, 2D and 3D diffusion for core were used in SRAC95. The system consists of several nuclear data libraries derived from ENDF/B-IV, -VI(R2 and R5), JENDL-3.1, JENDL-3.2, and JEF-2.2. Modified versions of five modular codes are integrated into SRAC95: collision probability calculation module(PIJ) for 16 types of lattice geometries, Sn transport calculation modules (ANISN, TWOTRAN), diffusion calculation modules (TUD, CITATION) and two optional codes for fuel assembly and core burn-up calculations (newly developed ASMBURN, revised COREBN).

Unusual features of the program include: Flexible energy group structure in cell and core calculation. 13 types of cell geometries for collision probability method. Optional treatments for resonance absorption by table look up based on NR or IR, or the continuous energy cell calculation in dominant resonance energy range. Successive cell calculation to treat double heterogeneity.

6. RESTRICTIONS OR LIMITATIONS

Restriction on the complexity of the problem : 20 regions for a continuous energy resonance absorption calculation and 16 steps for cell burn up.

7. TYPICAL RUNNING TIME

It depends on the number of energy group, geometry option, and with or without burn up calculation.

8. COMPUTER HARDWARE REQUIREMENTS

The code has been tested on HP, IBM, NEC, FACOM, Sun Solaris and PC Pentium computers.

9. COMPUTER SOFTWARE REQUIREMENTS

SRAC95 can be run on almost any UNIX or Linux operating system supporting a Fortran 77 compiler. SRAC95 is available on scalar or vector computers with the UNIX operating system or its similar ones (Linux/FreeBSD). At RSICC SRAC95 was tested on PC Pentium Linux operating system.

10. REFERENCES

a: included in document:

K. Tsuchihashi, Y. Ishiguro, K. Kaneko, and M. Idom "Revised SRAC Code System," JAERI 1302 (1986) (in English but for old version SRAC).

T. Kugo, K. Tsuchihashi, H. Akie and H. Takano, "SRAC-EWS (Engineering WorkStation) Version of the SRAC Code," JAERI JW282 (1994) (in English).

b. background information:

K. Tsuchihashi, H. Takano, K. Horikami, Y. Ishiguro, "SRAC: JAERI Thermal Reactor Standard Code System for Reactor Design and Analysis," JAERI 1285 (1983).

11. CONTENTS OF CODE PACKAGE

Included are the referenced documents in 10.a on one CD which also contains the source, test cases, and data libraries in a Unix tar file (approximately 172 MB.)

12. DATE OF ABSTRACT

April 2003.

KEYWORDS: BURNUP; ISOTOPE INVENTORY; FISSION PRODUCT INVENTORY; FUEL MANAGEMENT