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#

neutronics

Here are 38 public repositories matching this topic...

A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools

  • UpdatedMar 18, 2025
  • Jupyter Notebook

Meshing library for nuclear workflows

  • UpdatedNov 22, 2024
  • Python
SCONE

Stochastic Calculator Of Neutron transport Equation

  • UpdatedJan 25, 2025
  • Fortran
MontePy

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

  • UpdatedMar 18, 2025
  • Python

Create parametric 3D fusion reactor CAD models

  • UpdatedSep 23, 2021

Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files

  • UpdatedFeb 7, 2025
  • Python

List of open source projects related to OpenMC

  • UpdatedAug 28, 2024

Openmc-FEnicsx for muLtiphysics tutorIAl

  • UpdatedJul 29, 2024
  • Jupyter Notebook

Combines open source packages to produce an automated fusion specific neutronics workflow

  • UpdatedMay 31, 2022
  • Python

Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis

  • UpdatedMar 19, 2021
  • C#

A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.

  • UpdatedMay 9, 2024
  • Python

The package for reading mcnp input in a pythonic way

  • UpdatedJul 25, 2022
  • Python

A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.

  • UpdatedApr 14, 2024
  • Python

DIF3D plugin to the ARMI nuclear reactor analysis framework

  • UpdatedJun 16, 2022
  • Python

A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC

  • UpdatedDec 9, 2022
  • Python

A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.

  • UpdatedAug 15, 2023
  • Python

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