OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology. OpenMC uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reacto...
| Main Authors: | , , , , , |
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| Other Authors: | |
| Format: | Article |
| Language: | English |
| Published: |
EDP Sciences,
2017-06-14T14:29:20Z.
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| Subjects: | |
| Online Access: | Get fulltext |