OpenMC Monte Carlo Code

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

Meshing library for nuclear workflows

Stochastic Calculator Of Neutron transport Equation

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

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

MC/DC: Monte Carlo Dynamic Code

Create parametric 3D fusion reactor CAD models

List of open source projects related to OpenMC

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

THOR is a radiation transport code for unstructured meshes.

Openmc-FEnicsx for muLtiphysics tutorIAl

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

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

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

No description provided.

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

The package for reading mcnp input in a pythonic way

MCNP SDEF to OpenMC conversion tool

DIF3D plugin to the ARMI nuclear reactor analysis framework

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

Energy-dependent neutron transport Monte Carlo implemented in Rust.

This is a Python package for fast conversion of STEP files to DAGMC models.

Create an arbitrary parametric tokamak neutron source

A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes

a tool for creating axially symetric CSG geometry

A Python package for creating publication quality plots for neutron / photon / particle spectrum

Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations

Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.

C library for loading, querying, visualizing, and converting MCNP and OpenMC CSG geometry models