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Computer Code Name: MNYCP
Computer Code Number: D00216
00
Keywords:
dosimetry cross sections
mcnp format
reaction cross sections
fission product cross sections
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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
.
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