1. NAME AND TITLE

MCRAC: Multiple Cycle Reactor Analysis Code.

2. CONTRIBUTOR

Ruder Boskovic Institute, Zagreb, Yugoslavia, through the NEA Data Bank, France.

3. CODING LANGUAGE AND COMPUTER

Fortran 77; IBM PC.

4. NATURE OF PROBLEM SOLVED

MCRAC is an in-core fuel management code to be used principally for scoping purposes. It performs both reactor nucleonic and economic analyses over multiple reactor cycles. MCRAC was converted from the IBM mainframe version as developed at Pennsylvania State University (originally written in Fortran IV).

5. METHOD OF SOLUTION

MCRAC uses a two-dimensional, two-group reactor model, and requires cross section sets in the form of polynomial functions of burnup. The main features are: multiple cycle depletion analysis, multiple cycle fuel cost analysis, 1.5-group neutron diffusion modelling, critical soluble boron concentration search, BOC power distribution flattening option, control rod or BPR simulation and spatial power dependent xenon-135 distribution calculation.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

The sample input was tested at NEA Data Bank on an IBM PC/AT with an 80287 math coprocessor. It took 39 minutes and 30 seconds.

8. COMPUTER HARDWARE REQUIREMENTS

MCRAC runs on an IBM PC, IBM PC/XT, IBM PC/AT and PC 386 with a math co-processor.

9. COMPUTER SOFTWARE REQUIREMENTS

The code was written in Fortran 77. The Microsoft Fortran version 5.0 compiler is used.

10. REFERENCES

B. G. Petrovic, D. Pevec and S. H. Levine, "MCRAC (RBI PC Version 89.4), Input Manual," IAEA0889 (March 12, 1990).

H. Y. Huang, J. P. Colletti, Z. H. Kodah and S. S. Kim, "MCRAC - Multiple Cycle Reactor Analysis Code" (as it appears in IAEA0889 document) (March 12, 1990).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2 MB) DOS diskette.

12. DATE OF ABSTRACT

November 1990.