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    28 repositories

    • mckit

      Public
      Tools to work with MCNP models and results
      tallynuclear-engineeringmcnpradiation-physicsmeshtally
      Jupyter Notebook
      •
      GNU General Public License v3.0
      •4•7•1•1•Updated Nov 15, 2024Nov 15, 2024

    • map-stp

      Public
      Transfer meta information on cells from an STP file to MCNP model. Set materials and densities according to tags specified in STP model tree.
      mcnpstp
      Python
      •
      MIT License
      •2•3•1•5•Updated Nov 15, 2024Nov 15, 2024

    • xpypact

      Public
      Python workflow framework for FISPACT
      Jupyter Notebook
      •
      MIT License
      •0•2•1•6•Updated Nov 15, 2024Nov 15, 2024

    • mckit-meshes

      Public
      A Python package to work with MCNP meshtallies and weight meshes
      Python
      •
      MIT License
      •0•0•0•9•Updated Nov 15, 2024Nov 15, 2024

    • mckit-nuclides

      Public
      Python code to work with elements and their isotopes
      Python
      •
      MIT License
      •0•0•0•5•Updated Nov 15, 2024Nov 15, 2024

    • openmc_mcnp_adapter

      Public
      Tool for converting MCNP input files to OpenMC classes/XML
      Python
      •
      MIT License
      •18•0•0•0•Updated May 27, 2024May 27, 2024

    • GEOUNED

      Public
      Current version of the code
      Python
      •
      European Union Public License 1.2
      •31•0•0•0•Updated May 24, 2024May 24, 2024

    • openmc

      Public
      OpenMC Monte Carlo Code
      Python
      •
      Other
      •503•0•0•0•Updated May 21, 2024May 21, 2024

    • parametrized-tokamak-source

      Public
      Create OpenMC source definition from tabulated plasma parameters
      Python
      •0•8•0•0•Updated Feb 26, 2024Feb 26, 2024

    • iWW-GVR

      Public
      A tool to manipulate MCNP weight window (WW) and to generate Global Variance Reduction (GVR) parameters
      Python
      •
      Other
      •7•0•0•0•Updated Feb 5, 2024Feb 5, 2024

    • MontePy

      Public
      Make objects not regexes. A python library to read, edit, and write MCNP input files.
      Python
      •
      MIT License
      •7•0•0•0•Updated Jan 16, 2024Jan 16, 2024

    • aioduckdb

      Public
      asyncio bridge to the duckdb library
      Python
      •
      MIT License
      •95•0•0•0•Updated Oct 11, 2023Oct 11, 2023

    • mc-tools

      Public
      Some Monte Carlo tools
      Python
      •
      GNU Lesser General Public License v3.0
      •17•0•0•0•Updated Feb 6, 2023Feb 6, 2023

    • travleev-numjuggler

      Public
      Tool to rename cells, surfaces, materials and universes in MCNP input files.
      Python
      •
      GNU General Public License v3.0
      •12•0•0•0•Updated Dec 5, 2022Dec 5, 2022

    • mcnptools

      Public
      C++
      •16•0•0•0•Updated Sep 9, 2022Sep 9, 2022

    • DAGMC

      Public
      Direct Accelerated Geometry Monte Carlo Toolkit
      C++
      •
      Other
      •65•0•0•0•Updated May 30, 2022May 30, 2022

    • csg2csg

      Public
      Tools to translate between different CSG geometry types
      Python
      •
      European Union Public License 1.2
      •24•0•0•0•Updated Apr 25, 2022Apr 25, 2022

    • PyTables

      Public
      A Python package to manage extremely large amounts of data
      Python
      •
      BSD 3-Clause "New" or "Revised" License
      •273•0•0•0•Updated Apr 19, 2022Apr 19, 2022

    • openmc-plotter

      Public
      Native plotting GUI for model design and verification
      Python
      •
      MIT License
      •18•0•0•0•Updated Apr 18, 2022Apr 18, 2022

    • neutronics_material_maker

      Public
      A tool for making reproducible materials and standardizing use across several neutronics codes
      Python
      •
      MIT License
      •11•0•0•0•Updated Feb 24, 2022Feb 24, 2022

    • JADE

      Public
      JADE, a novel nuclear data libraries V&V tool
      Python
      •
      GNU General Public License v3.0
      •8•0•0•0•Updated Jan 31, 2022Jan 31, 2022

    • openmc-plasma-source

      Public
      Creates a plasma source as an openmc.source object from input parameters that describe the plasma
      Python
      •
      MIT License
      •11•0•0•0•Updated Nov 10, 2021Nov 10, 2021

    • networkx

      Public
      Network Analysis in Python
      Python
      •
      Other
      •3.3k•0•0•0•Updated Aug 10, 2021Aug 10, 2021

    • ONIX

      Public
      ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers coupling with the open-source transport code OpenMC.
      Python
      •
      MIT License
      •13•0•0•0•Updated Jul 27, 2021Jul 27, 2021

    • SpaceClaim_API_NeutronicsTools

      Public
      Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
      C#
      •
      MIT License
      •8•0•0•0•Updated Mar 19, 2021Mar 19, 2021

    • parametric-plasma-source

      Public
      Source and build files for parametric plasma source for use in fusion neutron transport calculations.
      C++
      •
      MIT License
      •6•0•0•0•Updated Nov 10, 2020Nov 10, 2020

    • SpaceClaim_scripts

      Public
      Assitant script for accelerating the modeling
      Python
      •
      MIT License
      •5•0•0•0•Updated Jul 30, 2020Jul 30, 2020

    • ERSN-OpenMC

      Public
      ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Bakkali & Tarek EL Bardouni, members of Radiation and Nuclear Systems Group ERSN at University Abdelmalek Essaady in Tetouan (Morocco).
      Java
      •21•0•0•0•Updated Jul 30, 2017Jul 30, 2017