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

Technical Report · Tue Jun 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7143331· OSTI ID:7143331

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

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.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7143331
• Report Number(s): ANL-8144; ENDF-239
• Country of Publication: United States
• Language: English

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