Package Details


Computer Code Name: MATXS7A

Computer Code Number: D00117

69-Group Thermal-Reactor Neutron Cross Section Data from ENDF/B-V in MATXS Format

Keywords:
multigroup cross sections
neutron cross sections
based on endf/b-v


Computers:
CDC


Operating Systems:

Languages:

Publications:
INFORMAL NOTES (RSIC)


Distribution Media:
D00117 C0000 -----1 TAPE CARTRIDGE TAR
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.