Development and benchmarking of higher energy neutron transport data libraries

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:7124448

Arthur, E D; Young, P G; Perry, R T; Madland, D G; MacFarlane, R E; Little, R C; Bozoian, M; LaBauve, R J

Neutron cross-section evaluations covering the energy range from 10/sup /minus/11/ to 100 MeV have been prepared for several materials. The principal method used to generate this data base has employed statistical-preequilibrium nuclear models, sophisticated phase shift analyses, and R-matrix techniques. The library takes advantage of formats developed for Version 6 of the Evaluated Nuclear Data File, ENDF. Methods to efficiently utilize the ENDF/B-VI representation of this library in the MCNP Monte Carlo code have been developed. MCNP results using the new library have been compared with calculated results using codes or data based upon intranuclear cascade models. 7 refs., 8 figs.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 7124448
• Report Number(s): LA-UR-88-1762; CONF-8805171-1; ON: DE88014473; TRN: 88-031331
• Resource Relation: Conference: International conference on nuclear data for science and technology, San Diego, CA, USA, 30 May 1988; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
BENCHMARKS
CROSS SECTIONS
EVALUATION
NUCLEAR MODELS
PHASE SHIFT
R MATRIX
MATHEMATICAL MODELS
MATRICES
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
651000* - Nuclear Physics