Computer Code Name: MATXS10

Computer Code Number: D00176

Neutron, Photon Cross Sections from ENDF/B-IV in MATXS Format.

Keywords:
kerma factors
matxs format
based on endf/b-vi
multigroup cross sections based on endf/b
neutron cross sections
gamma-ray cross sections
coupled neutron-gamma-ray cross sections

Computers:
ALLCP

Operating Systems:
SUN

Languages:
FORTRAN 77

Publications:
EXTRACTS FROM LA-12312-MS
LA-UR-94-1284

Distribution Media:
D00176 ALLCP -----1 TAPE CARTRIDGE TAR
D00176 ALLCP -----3 DS/HD 5.25 (1.2MB) DOS

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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.