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

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☢ Awesome Nuclear ☢

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

Particle Transport

Codes: Monte Carlo

  • 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

Codes: Deterministic

  • BART — Finite-element, discrete ordinates code developed by UC-Berkeley
  • Chi-Tech — Parallel discrete ordinates code developed by Texas A&M
  • DRAGON — Lattice code developed by Polytechnique Montreal
  • FeenoX — Unstructured finite-element(ish) tool, diffusion and discrete ordinates
  • OpenMOC — Method of characteristics code
  • THOR — Discrete ordinates code using the AHOT-C method on unstructured meshes

Codes: Event Generators

  • CGMF — Fission event generator
  • FREYA — Fission event generator

Related Tools

  • 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

Nuclear Data

  • 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

Depletion / Transmutation / Decay

  • 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

Kinetics

  • 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

Fuel Cycle

  • Cyclus — Nuclear fuel cycle simulator
  • OpenMCyclus — Depletable reactor archetype using OpenMC's IndependentOperator for fuel cycle simulations in Cyclus

Thermal Hydraulics

  • DASSH — Subchannel thermal fluids code for hexagonal assemblies
  • 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.

Multiphysics

  • 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

Molten Salt Reactor

  • Moltres — A molten salt reactor simulator code
  • MSRE — Detailed CAD model of the MSRE
  • SaltProc — Fuel reprocessing simulation tool

Other

Research Groups Invested in Open Source Tools for Nuclear Science and Engineering

  • 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.