Computer Code Name: ALLCP

Computer Code Number: D00175

01

Keywords:
kerma factors
benchmark problem cross sections
concrete cross sections
anisn format
coupled neutron-gamma-ray cross sections
multigroup cross sections
multigroup cross sections based on endf/b
neutron cross sections
detector response
based on endf/b-vi

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Operating Systems:

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Publications:
ORNL-6795 (DRAFT 4/94)

Distribution Media:

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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.