Comparison of Monte Carlo Methods for Criticality Benchmarks: Pointwise Compared to Multigroup

Conference · Sun Jun 04 04:00:00 EDT 1989 · Transactions of the American Nuclear Society

OSTI ID:5237341

Transport codes use multigroup cross sections where neutrons are divided into broad energy groups, and the monoenergetic equation is solved for each group with a group-averaged cross section. Monte Carlo codes differ in that they allow the use of the most basic pointwise cross-section data directly in a calculation. Most of the first Monte Carlo codes were not able to utilize this feature, however, because of the memory limitations of early computers and the lack of pointwise cross-section data. Consequently, codes written in 1970s, such as KENO-IV and MORSE-C, were adapted to use multigroup cross-section sets similar to those used in the S_n transport codes. With advances in computer memory capacities and the availability of pointwise cross-section sets, new Monte Carlo codes employing pointwise cross-section libraries, such as the Los Alamos National Laboratory code MCNP and the Lawrence Livermore National Laboratory (LLNL) code COG were developed for criticality, as well as radiation transport calculations. To compare pointwise and multigroup Monte Carlo methods for criticality benchmark calculations, this paper presents and evaluated the results from the KENO-IV, MORSE-C, MCNP, and COG codes. The critical experiments selected for benchmarking include LLNL fast metal systems and low-enriched uranium moderated and reflected systems.

• Research Organization: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5237341
• Report Number(s): CONF-890604--
• Conference Information: Journal Name: Transactions of the American Nuclear Society Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420203* -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
AQUEOUS SOLUTIONS
BENCHMARKS
CALCULATION METHODS
COG
CRITICALITY
CROSS SECTIONS
DISPERSIONS
GROUP THEORY
KENO-IV
LASL
LAWRENCE LIVERMORE LABORATORY
MATHEMATICS
MIXTURES
MODERATORS
MONTE CARLO METHOD
MORSE-C
MULTIPLICATION FACTORS
Monte Carlo Codes
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
Nuclear Criticality Safety Program (NCSP)
RADIATION TRANSPORT
SOLUTIONS
Transport codes
US AEC
US DOE
US ERDA
US ORGANIZATIONS