Package Details


Computer Code Name: MNYCP

Computer Code Number: D00210

00

Keywords:
based on endf/b-v
based on endf/b-vi
burnup
fission product yields
neutron cross sections


Computers:

Operating Systems:

Languages:

Publications:
RC-1442, COG-I-95-200


Distribution Media:
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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