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Preparation and Benchmarking of ANSL-V Cross Sections for Advanced Neutron Source Reactor Studies

Conference · · Transactions of the American Nuclear Society
OSTI ID:6868423
Research and development for the advanced neutron source (ANS) reactor is being funded by the US Dept. of Energy. This reactor is to provide the world's most intense steady-state source of low-energy neutrons for a national experimental user facility. Pseudo-problem-independent, multigroup cross-section libraries were generated to support ANS design work. The libraries, designated ANSL-V, are data bases in AMPX master format for subsequent generation of problem-dependent cross sections for use with codes such as KENO, ANISN, XSDRNPM, VENTURE, DOT, and MORSE. Included in ANSL-V are 123-material P3 neutron, 46-material P0 or P6 secondary gamma-ray production (SGRP), and 34-material P6 gamma-ray interaction (GRI) libraries.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
6868423
Report Number(s):
CONF-8711195-
Conference Information:
Journal Name: Transactions of the American Nuclear Society Journal Volume: 55
Country of Publication:
United States
Language:
English