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) 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.