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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
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PC X86
MACINTOSH
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D00248 MNYCP -----2 DVD-R
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Security Notice
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
.