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

By P. Romano, N. Horelik, B. Herman, Adam Nelson, B. Forget, Kord Smith. International Conference on Supercomputing, 2014

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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 reactors and other systems. Modern, portable input/output file formats are used in OpenMC: XML for input, and HDF5 for output. High performance parallel algorithms in OpenMC have demonstrated near-linear scaling to over 100,000 processors on modern supercomputers. Other topics discussed in this paper include plotting, CMFD acceleration, variance reduction, eigenvalue calculations, and software development processes.

Subfields: Aerospace Engineering, Materials Chemistry, Radiation

View Paper: https://www.semanticscholar.org/paper/2ccc0aa6c1f424e53948c7ad18803707b1737527