Computer Code Name: TENDL-2012-ACE

Computer Code Number: D00266

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:
TENDL-2009: on Evaluations and Monte Carlo Covariances

Distribution Media:
D00266 MNYCP -----2 DVD-R

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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.