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Open Nodal Core Simulator
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
Energy-dependent neutron transport Monte Carlo implemented in Rust.
Test code for 2D transient neutron diffusion equation based on the finite difference method (FDM) and stiffness confinement method (SCM).
An open source nodal solver for nuclear reactors.
One Dimensional Neutron Diffusion Equation for Slab, Cylindrical, and Sphere Geometries.
Numerical simulation of the neutron diffiusion in a nuclear reactor.
Deterministic 2-group neutron diffusion solver for reactor core analysis
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