Computer Code Name: MNYCP

Computer Code Number: P00194

01

Keywords:
endf format
multigroup cross sections
neutron cross section processing
reactor physics

Computers:

Operating Systems:

Languages:

Publications:
FTN 4.8+528
IJS-DP-4368 (8/86)
INDC(YUG)-9/GV (4/84)
KFKI-1981-34 AND FEDGROUP MANUAL

Distribution Media:

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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.