Computer Code Name: ANSL-V

Computer Code Number: D00154

ENDF/B-V Based Multigroup Cross Section Libraries for Advanced Neutron Source (ANS) Reactor Studies.

Keywords:
based on endf/b-v
gamma-ray production data
multigroup cross sections
neutron cross sections
gamma-ray cross sections

Computers:
IBM RS/6000

Operating Systems:

Languages:

Publications:
ORNL-6618
ORNL-6618/S1

Distribution Media:
D00154 ALLCP -----1 TAPE CARTRIDGE TAR
D00154 ALLCP -----1 MODE 1 CDROM TAR OR DOS
D00154 ALLCP -----1 TAPE CARTRIDGE 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.