A curated list of open source projects used in nuclear science and engineering

A curated list of open source projects used in nuclear science and engineering.

- ERGnrc — Monte Carlo photon/electron/positron transport code

- FRENSIE — Monte Carlo neutron/photon transport code

- Geant4 — High-energy Monte Carlo particle transport code

- OpenMC — Monte Carlo neutron/photon transport code

- SCONE — Monte Carlo neutron transport code

- Warp — Monte Carlo neutron transport code on GPUs

- BART — Finite-element, discrete ordinates code developed by UC-Berkeley

- DRAGON — Lattice code developed by Polytechnique Montreal

- FeenoX — Unstructured finite-element(ish) tool, diffusion and discrete ordinates

- Gnat — A MOOSE-based discrete ordinates and fluid activation solver developed by Ontario Tech

- OpenMOC — Method of characteristics code

- OpenSN — Successor to Chi-Tech, a massively parallel discrete ordinates code developed by Texas A&M

- Scarabée — Lattice physics code and deterministic transport toolbox

- THOR — Discrete ordinates code using the AHOT-C method on unstructured meshes

- ACE Format — Documentation of the ACE format

- csg2csg — Tool to translate between different CSG types

- DAGMC — Direct accelerated geometry Monte Carlo toolkit

- GeoUNED — FreeCAD-based tool to convert from CAD to CSG and vice versa

- KDSource — A tool for generating KDE surface sources from Monte Carlo simulations

- McCAD — C++ Library for CAD (BRep) to Monte Carlo (CSG) Conversion

- MCNPTools — C++/Python interface and tools for MCNP

- MCPL — Binary file format for storing particle state

- MontePy — Python library to read, edit, and write MCNP files

- serpentTools — Python-based tool suite for Serpent

- t4_geom_convert — Convert MCNP geometries to TRIPOLI-4

- ACEMAKER — Code package to produce ACE files

- EMPIRE — Nuclear reaction model code

- endf-python — Python ENDF Parser

- FRENDY — Nuclear data processing

- FUDGE — Python-based nuclear data processing

- JADE — Tool for nuclear data library V&V

- mendeleev — Python package for accessing properties of elements, ions, and isotopes

- NJOY21 — Nuclear data processing

- Nuclear Data Reader — C++ library for parsing NUBASE and AME data files

- NucML — Machine-learning pipeline for nuclear data evaluation

- PapillonNDL — C++ / Python library for reading and sampling ACE files

- PREPRO — Nuclear data processing

- PyNjoy 2012 — Nuclear data processing

- SANDY — Sampling tool for nuclear data

- SCALE — Public components of SCALE (AMPX, SAMMY)

- TALYS — Nuclear Reaction Simulator Code

- ADDER — Python-based fuel management and depletion tool

- ALARA — Activation code widely used for fusion

- ONIX — Python-based burnup code

- OpenMC — Depetion solver integrated in OpenMC

- radioactivedecay — Radioactive decay solver

- KOMODO — Nuclear reactor simulator that solves 3-D diffusion using nodal methods

- PyRK — Neutronic and thermal hydraulic reactor transient analysis in 0-D

- Research Reactor Simulator — Real-time GUI research reactor simulator based on point kinetics

- Cyclus — Nuclear fuel cycle simulator

- OpenMCyclus — Depletable reactor archetype using OpenMC's IndependentOperatorfor fuel cycle simulations in Cyclus

- Nek5000 — Spectral-element CFD code

- nekRS — Spectral-element CFD code targeting modern processors and accelerators

- OpenFOAM — Finite volume CFD code

- TrioCFD — A Computational Fluid Dynamics (CFD) code based on the TRUST platform.

- Aurora — OpenMC wrapped as a MOOSE app

- Cardinal — OpenMC and nekRS wrapped as MOOSE apps

- ENRICO — Monte Carlo + CFD coupling application

- GeN-Foam — OpenFOAM based multi-physics solver for reactor analysis

- MOOSE — Finite-element, multiphysics framework

- SALOME — Interoperability between CAD and multiphysics software

- TRUST — A software platform upon which CFD codes can be built

- Moltres — A molten salt reactor simulator code

- MSRE — Detailed CAD model of the MSRE

- SaltProc — Fuel reprocessing simulation tool

- ARMI — Reactor analysis automation framework

- NRIC Virtual Test Bed — Repository of example challenge problems

- PyARC — Fast reactor analysis workflows using the Argonne Reactor Computation code suite

- PyNE — Python/C++ nuclear engineering toolkit

- RAVEN — UQ, regression, PRA, data analysis, and model optimization framework

- WATTS — Python-based tool for templated simulations

- 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.