Computer Code Name: TENDL-2008-ACE

Computer Code Number: D00243

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

Keywords:
mcnp format
neutron cross sections

Computers:
MANY COMPUTERS

Operating Systems:
LINUX
WINDOWS
UNIX

Languages:

Publications:
JEFF-DOC 1262 (November 17, 2008)

Distribution Media:
D00243 MNYCP -----1 DVD

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.