Package Details


Computer Code Name: CANDULIB-AECL

Computer Code Number: D00210

Burnup-Dependent ORIGEN-S Cross Section Libraries for CANDU Reactor Fuel Characterization

Keywords:
based on endf/b-v
based on endf/b-vi
burnup
fission product yields
neutron cross sections


Computers:
PENTIUM
IBM RS/6000


Operating Systems:
UNIX
WINDOWS


Languages:

Publications:
RC-1442, COG-I-95-200


Distribution Media:
D00210 MNYCP -----2 DS/HD 3.5(1.44M)DOS+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.