Preparation and Benchmarking of ANSL-V Cross Sections for Advanced Neutron Source Reactor Studies
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:6868423
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
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
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
97 MATHEMATICS AND COMPUTING
AMPX
ANSL-V
Advanced Neutron Source (ANS) Reactor
BENCHMARKS
CROSS SECTIONS
GROUP THEORY
KINETICS
MATHEMATICS
NATIONAL ORGANIZATIONS
NEUTRON SOURCES
NUCLEAR DATA COLLECTIONS
National Experimental User Facility
Nuclear Criticality Safety Program (NCSP)
PARTICLE SOURCES
RADIATION SOURCES
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
US DOE
US ORGANIZATIONS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
97 MATHEMATICS AND COMPUTING
AMPX
ANSL-V
Advanced Neutron Source (ANS) Reactor
BENCHMARKS
CROSS SECTIONS
GROUP THEORY
KINETICS
MATHEMATICS
NATIONAL ORGANIZATIONS
NEUTRON SOURCES
NUCLEAR DATA COLLECTIONS
National Experimental User Facility
Nuclear Criticality Safety Program (NCSP)
PARTICLE SOURCES
RADIATION SOURCES
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
US DOE
US ORGANIZATIONS