Package Details


Computer Code Name: CALENDF-2010

Computer Code Number: P00578

Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations

Keywords:
endf/b-vi
endf format
multigroup cross section processing
neutron cross section processing
r-matrix theory


Computers:
SUN
PC X86
MACINTOSH


Operating Systems:
LINUX
WINDOWS
UNIX
OSX
SOLARIS


Languages:
FORTRAN 90
FORTRAN 95


Publications:
CEA-R-6277,CEA-R-6227,LA-UR-08-4668,CEA-R-6100


Distribution Media:
P00578 PCX86 -----1 CD-ROM DISC
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.