The OpenMC Monte Carlo particle transport code
Author(s)Romano, Paul Kollath; Forget, Benoit Robert Yves
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A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute of Technology as a tool for simulation on high-performance computing platforms. Given that many legacy codes do not scale well on existing and future parallel computer architectures, OpenMC has been developed from scratch with a focus on high performance scalable algorithms as well as modern software design practices. The present work describes the methods used in the OpenMC code and demonstrates the performance and accuracy of the code on a variety of problems.
DepartmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
Annals of Nuclear Energy
Romano, Paul K. and Forget, Benoit. “The OpenMC Monte Carlo Particle Transport Code.” Annals of Nuclear Energy 51 (January 2013): 274–281. © 2012 Elsevier Ltd
Author's final manuscript