A curated list of open source projects used in nuclear science and engineering.
- BART — Finite-element, discrete ordinates code developed by UC-Berkeley
- CGMF — Fission event generator
- Dragon — Lattice code developed by Polytechnique Montreal
- ERGnrc — Monte Carlo photon/electron/positron transport code
- FRENSIE — Monte Carlo neutron/photon transport code
- FREYA — Fission event generator
- Geant4 — High-energy Monte Carlo particle transport code
- milonga — Finite-element and finite-volume, diffusion and discrete ordinates code
- OpenMC — Monte Carlo neutron/photon transport code
- OpenMOC — Method of characteristics code
- SCONE — Monte Carlo neutron transport code
- Warp — Monte Carlo neutron transport code on GPUs
- ACE Format — Documentation of the ACE format
- csg2csg — Tool to translate between different CSG types
- DAGMC — Direct accelerated geometry Monte Carlo toolkit
- serpent-tools — Python-based tool suite for Serpent
- EMPIRE — Nuclear reaction model code
- FRENDY — Nuclear data processing
- FUDGE — Python-based nuclear data processing
- NJOY21 — Nuclear data processing
- PREPRO — Nuclear data processing
- PyNjoy 2012 — Nuclear data processing
- SANDY — Sampling tool for nuclear data
- TALYS — Nuclear Reaction Simulator Code
- KOMODO — Nuclear reactor simulator that solves 3-D diffusion using nodal methods
- PyRK — Neutronic and thermal hydraulic reactor transient analysis in 0-D
- Cyclus — Nuclear fuel cycle simulator
- Nek5000 — Spectral-element CFD code
- nekRS — Spectral-element CFD code targeting modern processors and accelerators
- OpenFOAM — Finite volume CFD code
- ENRICO — Monte Carlo + CFD coupling application
- MOOSE — Finite-element, multiphysics framework
- Okapi — OpenMC wrapped as a MOOSE app
- SALOME — Interoperability between CAD and multiphysics software
- Moltres — A molten salt reactor simulator code
- PyNE — Python/C++ nuclear engineering toolkit
- ARMI — Reactor analysis automation framework
- LaTeX classes and BibTeX style for ANS publications
- ARFC (UIUC) — Advanced Reactors and Fuel Cycles
- CNERG (UW-Madison) — Computational Nuclear Engineering Research Group
- CRPG (MIT) — Computational Reactor Physics Group
- ONCORE (IAEA) — an IAEA-facilitated international collaboration framework for the development and application of open-source multi-physics simulation tools to support research, education and training for the analysis of advanced nuclear power reactors.