Computer Code Name: UTXS6

Computer Code Number: D00211

MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.

Keywords:
reaction cross sections
dosimetry cross sections
mcnp format
fission product cross sections

Computers:
ALL WORKSTATION

Operating Systems:
UNIX

Languages:

Publications:
ANRCP-1999-28
Informal Notes

Distribution Media:
D00211 MNYCP -----1 CD-ROM TAR

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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.