Computer Code Name: TENDL-2010-ACE

Computer Code Number: D00248

TALYS-Based Cross Section Library for Use with MCNP(X).

Keywords:
mcnp format
neutron cross sections

Computers:
PC X86
MACINTOSH
WORKSTATIONS

Operating Systems:

Languages:

Publications:

Distribution Media:
D00248 MNYCP -----2 DVD-R

123ABCDEFGHIJKLMNOPQRSTUVWXYZ

The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.