Computer Code Name: ALLCP

Computer Code Number: D00185

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

Computers:

Operating Systems:

Languages:

Publications:
ORNL-6795, R 1, NUREG/CR-6214, REVISION 1

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.