Package Details


Computer Code Name: MNYCP

Computer Code Number: D00223

01

Keywords:
mcnp format
based on jendl
evaluated neutron cross sections
neutron cross sections


Computers:

Operating Systems:

Languages:

Publications:
JAERI-Data/Code 2003-011


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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