1. NAME AND TITLE
MORSE-C: Monte Carlo Multigroup Neutron Code System for the Solution of Criticality
Problems. We recommend C00474/ALLCP/02 MORSE-CGA.
N92GRP: 92-group library obtained from the LLNL ENDL compilation existing in November
Lawrence Livermore National Laboratory, Livermore, California.
3. CODING LANGUAGE AND COMPUTER
4. NATURE OF PROBLEM SOLVED.
MORSE-C is based on the original ORNL versions of CCC-127/MORSE and CCC-261/MORSE-L
but is restricted to criticality problems. Continued efforts in criticality safety calculations led to the
development of techniques which resulted in improvements in energy resolution of cross sections,
upscatter in the thermal region, and a better cross section library. Only time-independent problems
are treated in the packaged version.
5. METHOD OF SOLUTION
Monte Carlo methods are used to solve the Boltzmann neutron transport equation in order to obtain
the eigenvalue when fissionable materials are present. Cross-sections are specified as multigroup,
multi-table values with up to a P3 Legendre expansion and 100 energy groups. Upscatter is allowed.
Geometry is specified in a general 3-D package with first and second degree surfaces and allowance
for array specifications. Pictures are drawn and volumes and masses calculated from the input
geometry definitions. Russian roulette and splitting can be utilized. Numerous output plots are made
to assist the user in understanding the physics of the problem being run.
6. RESTRICTIONS OR LIMITATIONS
The P0 cross-section table must not contain negative values.
7. TYPICAL RUNNING TIME
Running time depends upon the physical nature of the problem (the more thermal the system the
longer the running time), the geometrical complexity, and the desired accuracy. Typical problems
have run from 30 seconds to 45 minutes.
8. COMPUTER HARDWARE REQUIREMENTS
MORSE-C was written for the CDC-7600 with LLNL graphics devices.
9. COMPUTER SOFTWARE REQUIREMENTS
MORSE-C was written in LRLTRAN for a LLNL internal compiler, CHAT.
T. P. Wilcox, "MORSE-C, a CDC-7600 program assigned to solve nuclear criticality problems
by using the Monte-Carlo Method," UCID-18993 (January 1981).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code plus sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: COMPLEX GEOMETRY; CRITICALITY CALCULATIONS; CROSS SECTION PROCESSING; MONTE CARLO; MULTIGROUP; NEUTRON