OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

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...

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Bibliographic Details
Main Authors: Nelson, Adam G., Romano, Paul Kollath, Horelik, Nicholas Edward, Herman, Bryan R, Forget, Benoit Robert Yves, Smith, Kord S.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Language:en_US
Published: EDP Sciences 2017
Online Access:http://hdl.handle.net/1721.1/109853
https://orcid.org/0000-0002-1147-045X
https://orcid.org/0000-0003-1459-7672
https://orcid.org/0000-0003-2497-4312

Internet

http://hdl.handle.net/1721.1/109853
https://orcid.org/0000-0002-1147-045X
https://orcid.org/0000-0003-1459-7672
https://orcid.org/0000-0003-2497-4312

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