Testing of the ENDF/B-VI Neutron Data Library ENDF60 for use with MCNP®

Conference · Sun Sep 17 04:00:00 EDT 1995

OSTI ID:104782

Frankle, S. C. ^[1]; MacFarlane, R. E. ^[1]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation transport code MCNP4A, was released in the fall of 1994. It is comprised of 124 nuclide data files based on the ENDF/B-Vi evaluations through Release 2. Forty-eight percent of these materials are new or modified evaluations, while the balance are translations from ENDF/B-V. The new evaluations include most of the important materials for criticality safety calculations, and include significant enhancements such as more isotopic evaluations, better resonance-range representations, and the new correlated energy-angle distributions for emitted particles. As part of the overall quality assurance testing of the ENDF60 library, calculations for well-known benchmark assemblies were performed. The results of these calculations help the user to know how the combination of ENDF60 and MCNP4A will perform for real problems.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 104782
• Report Number(s): LA-UR--95-1886; CONF-9509100--28; ON: DE95015199
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
BENCHMARKS
CRITICALITY
ENDF/B-V
ENDF60
M CODES
MONTE CARLO METHOD
Monte Carlo N-Particle Radiation Transport Code MCNP4A
NEUTRON REACTIONS
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PERFORMANCE TESTING