Stochastic Calculator Of Neutron transport Equation
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Updated
Jan 25, 2025 - Fortran
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neutronics
Here are 3 public repositories matching this topic...
THOR is a radiation transport code for unstructured meshes.
computational-physics nuclear unstructured-meshes nuclear-engineering nuclear-physics neutron-transport particle-transport photon-transport radiation-transport neutronics discrete-ordinates-method nuclear-fission deterministic-transport
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Updated
Sep 17, 2024 - Fortran
An open source utility to convert various publicly available macroscopic nuclear cross section formats
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Updated
Aug 8, 2024 - Fortran
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