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OpenMC

Category: Other
Developers: Argonne National Laboratory


Product Description:OpenMC is an open-source, high-performance Monte Carlo code with a Python-native interface for simulating neutron and photon transport in complex nuclear systems, scalable from laptops to exascale supercomputers. OpenMC transforms high-fidelity simulation of neutron and photon transport from a niche, license-constrained domain into an open, Python-native framework that any scientist/engineer can deploy on machines ranging from laptops to exascale supercomputers. Its modern C++ core is fast, yet fully scriptable, enabling automated exploration of a design space, optimization through machine learning and visualization in real time. By supporting integrated depletion, CAD-based geometry, and automated workflows for variance reduction, shutdown dose rate, and cross section generation, OpenMC significantly simplifies tasks that once required multiple proprietary codes. By democratizing advanced reactor analysis and accelerating innovation in the fusion industry, OpenMC delivers accessibility, performance and community impact.


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