OpenMC Monte Carlo Code
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Updated
Dec 16, 2024 - Python
OpenMC Monte Carlo Code
Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303
A curated list of open source projects used in nuclear science and engineering
Celeritas is a new Monte Carlo transport code designed to accelerate scientific discovery in high energy physics by improving detector simulation throughput and energy efficiency using GPUs.
ENRICO: Exascale Nuclear Reactor Investigative COde
For shallow-water Lagrangian particle routing.
Native plotting GUI for model design and verification
MC/DC: Monte Carlo Dynamic Code
THOR is a radiation transport code for unstructured meshes.
Two phase particle transport model simulating formation damage in porous media
Project repository for "An Open Source Nuclear Modeling Ecosystem to Support Fusion Pilot Plant Design" collaboration between MIT and ANL
This repository contains a beginner-friendly tutorial for OpenMC, a Monte Carlo particle transport simulation code widely used in nuclear engineering.
Energy-dependent neutron transport Monte Carlo implemented in Rust.
(M)onte Carlo (I)nteraction and (D)osimetry (S)imulation of (X)-Rays. WIP senior thesis project at Saint Vincent College.
Test simulations of turbulent magnetic fields in CRPropa
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