Computer Code Name: MNYCP

Computer Code Number: D00229

01

Keywords:
based on endf/b-vi
damage cross sections
benchmark neutron fields
neutron cross sections
dosimetry cross sections
mcnp format
reaction cross sections

Computers:

Operating Systems:

Languages:

Publications:
IAEA-TECDOC-DRAFT

Distribution Media:

123ABCDEFGHIJKLMNOPQRSTUVWXYZ

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.