MORSE-C: A CDC-7600 Program Designed to Solve Nuclear Criticality Problems by Using the Monte-Carlo Method

摘要

This user's manual covers this latest version of the MORSE-C code which solves the multiple energy group form of the Boltzmann transport equation in order to obtain the eigenvalue (multiplication) when fissionable materials are present. Cross sections for up to 100 energy groups may be employed. The angular scattering is treated by the usual Legendre expansion as used in the discrete ordinates codes. Upscattering may be specified. The geometry is defined by relationships to general 1st or 2nd degree surfaces. Array units may be specified. Output includes, besides the usual values of input quantities, plots of the geometry, calculated volumes and masses, and graphs of results to assist the user in determining the correctness of the problem's solution. Appendix II of this report contains the code listing with its numerous comments which should simplify finding an answer to any specific question the reader might have about MORSE-C. The remaining sections of this report explain how to obtain the code, how to set-up the input for a specific problem, how to understand the output, and then illustrates two typical problems run with the code. (ERA citation 81:026025)