Package Details


Computer Code Name: TENDL-2011-ACE

Computer Code Number: D00252

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:
D00252 MNYCP -----1 DVD-9 Dual Layer
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.