Reactor physics verification of the MCNP6 unstructured mesh capability

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22212779

Burke, T. P. ^[1]; Kiedrowski, B. C.; Martz, R. L. ^[2]; Martin, W. R. ^[1]

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1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109 (United States)
2. X-Computational Physics Division, Monte Carlo Codes Group, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)

The Monte Carlo software package MCNP6 has the ability to transport particles on unstructured meshes generated from the Computed-Aided Engineering software Abaqus. Verification is performed using benchmarks with features relevant to reactor physics - Big Ten and the C5G7 computational benchmark. Various meshing strategies are tested and results are compared to reference solutions. Computational performance results are also given. The conclusions show MCNP6 is capable of producing accurate calculations for reactor physics geometries and the computational requirements for small lattice benchmarks are reasonable on modern computing platforms. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212779
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPUTER CODES
GEOMETRY
MATHEMATICAL SOLUTIONS
MESH GENERATION
MONTE CARLO METHOD
REACTOR PHYSICS
VERIFICATION