Multi-core performance studies of a Monte Carlo neutron transport code

Multi-core performance studies of a Monte Carlo neutron transport code

Performance results are presented for a multi-threaded version of the OpenMC Monte Carlo neutronics code using OpenMP in the context of nuclear reactor criticality calculations. Our main interest is production computing, and thus we limit our approach to threading strategies that both require reason...

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Bibliographic Details
Main Authors: Siegel, A. R. (Author), Felker, K. G. (Author), Smith, Kord S. (Contributor), Romano, Paul Kollath (Contributor), Forget, Benoit Robert Yves (Contributor)
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering (Contributor)
Format: Article
Language:English
Published: Sage Publications, 2017-03-24T15:43:03Z.
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