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. (Author), Romano, Paul Kollath (Contributor), Horelik, Nicholas Edward (Contributor), Herman, Bryan R (Contributor), Forget, Benoit Robert Yves (Contributor), Smith, Kord S. (Contributor)
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering (Contributor)
Format: Article
Language:English
Published: EDP Sciences, 2017-06-14T14:29:20Z.
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