1976•Unpublished venueOpen access

MC/sup 2/-2: a code to calculate fast neutron spectra and multigroup cross sections. [LMFBR]

H. Henryson, B.J. Toppel, C.G. Stenberg

Abstract

MC/sup 2/-2 is a program to solve the neutron slowing down problem using basic neutron data derived from the ENDF/B data files. The spectrum calculated by MC/sup 2/-2 is used to collapse the basic data to multigroup cross sections for use in standard reactor neutronics codes. Four different slowing down formulations are used by MC/sup 2/-2: multigroup, continuous slowing down using the Goertzel-Greuling or Improved Goertzel-Greuling moderating parameters, and a hyper-fine-group integral transport calculation. Resolved and unresolved resonance cross sections are calculated accounting for self-shielding, broadening and overlap effects. This document provides a description of the MC/sup 2/-2 program. The physics and mathematics of the neutron slowing down problem are derived and detailed information is provided to aid the MC/sup 2/-2 user in preparing input for the program and implementation of the program on IBM 370 or CDC 7600 computers.

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Key concepts: Neutron transport, Neutron, Physics, Nuclear data, Nuclear physics, Code (set theory), Resonance (particle physics), Spectral line