1. NAME AND TITLE
MCRAC: Multiple Cycle Reactor Analysis Code.
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
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.
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
KEYWORDS: CROSS SECTIONS; DIFFUSION THEORY; FUEL MANAGEMENT; MICROCOMPUTER; NEUTRON; REACTOR PHYSICS; TWO-DIMENSIONS