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
neutron cross section processing
r-matrix theory
multigroup cross section processing


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) 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.