Computer Code Name: TRANSX-CTR

Computer Code Number: P00206

Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis.

Keywords:
multigroup cross sections
self shielding
matxs format

Computers:
CRAY

Operating Systems:
UNICOS

Languages:
FORTRAN

Publications:
LA-9863-MS
LA-9983-MS

Distribution Media:
P00206 CY000 -----1 DS/DD 5.25 (360KB) DOS

123ABCDEFGHIJKLMNOPQRSTUVWXYZ

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.