Multi-core performance studies of a Monte Carlo neutron transport code
Name
Forget_Multi-core performance.pdf
Size
380.53 KB
Format
Adobe PDF
Checksum (MD5)
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Author(s)
Siegel, A. R.
Felker, K. G.
Smith, Kord S.
Romano, Paul Kollath
Forget, Benoit Robert Yves
Date Issued
July 2013
Journal
International Journal of High Performance Computing Applications
Publisher
Sage Publications
Citation
Siegel, A. R. et al. “Multi-Core Performance Studies of a Monte Carlo Neutron Transport Code.” International Journal of High Performance Computing Applications 28.1 (2014): 87–96.
Version
Original manuscript
Abstract
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 reasonable levels of development effort and preserve the code features necessary for robust application to real-world reactor problems. Several approaches are developed and the results compared on several multi-core platforms using a popular reactor physics benchmark. A broad range of performance studies are distilled into a simple, consistent picture of the empirical performance characteristics of reactor Monte Carlo algorithms on current multi-core architectures.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-Noncommercial-Share Alike
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1177/1094342013492179
