The OpenMOC method of characteristics neutral particle transport code
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Annals_OpenMOC.pdf
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931.66 KB
Format
Adobe PDF
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78987fc488556ad57877bf64d28e9a4b
Author(s)
Li, Lulu
Boyd III, William Robert Dawson
Shaner, Samuel Christopher
Forget, Benoit Robert Yves
Smith, Kord S.
Date Issued
January 2014
Journal
Annals of Nuclear Energy
Publisher
Elsevier
Citation
Boyd, William, Samuel Shaner, Lulu Li, Benoit Forget, and Kord Smith. “The OpenMOC Method of Characteristics Neutral Particle Transport Code.” Annals of Nuclear Energy 68 (June 2014): 43–52. ©2014
Version
Author's final manuscript
Abstract
The method of characteristics (MOC) is a numerical integration technique for partial differential equations, and has seen widespread use for reactor physics lattice calculations. The exponential growth in computing power has finally brought the possibility for high-fidelity full core MOC calculations within reach. The OpenMOC code is being developed at the Massachusetts Institute of Technology to investigate algorithmic acceleration techniques and parallel algorithms for MOC. OpenMOC is a free, open source code written using modern software languages such as C/C++ and CUDA with an emphasis on extensible design principles for code developers and an easy to use Python interface for code users. The present work describes the OpenMOC code and illustrates its ability to model large problems accurately and efficiently.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-NonCommercial-NoDerivs License
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1016/j.anucene.2013.12.012
