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OpenMC Software Advances Nuclear Fusion and Fission Reactor Simulations

DATA AND AI INFRASTRUCTUREFUSION & ADVANCED NUCLEAR POWER

OpenMC, developed by Argonne National Laboratory and MIT, is an open-source software that predicts subatomic particle behavior in reactor designs, enhancing safety and efficiency in nuclear fission and fusion. Awarded the R&D-100-Award, OpenMC enables virtual experiments to accelerate developments before costly prototypes.

Its adoption spans national labs, universities, and private firms, particularly in the US and Europe, supported by the DOE's Fusion Energy Sciences program. OpenMC has been optimized for exascale supercomputers, allowing precise simulations of reactors, with contributions from Argonne and MIT researchers.

OpenMC Software Advances Nuclear Fusion and Fission Reactor Simulations
Jan 22, 2026, 6:22 PM

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