The OpenMOC method of characteristics neutral particle transport code
Author(s)Li, Lulu; Boyd III, William Robert Dawson; Shaner, Samuel Christopher; Forget, Benoit Robert Yves; Smith, Kord S.
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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.
DepartmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
Annals of Nuclear Energy
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
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