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

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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.