A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles

A Python package that plots OpenMC geometry using web based technologies

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

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

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

A tool for making reproducible materials and standardizing use across several neutronics codes

Create axis slice plots of OpenMC geomtry with specified zoom

Creates a plasma source as an openmc.source object from input parameters that describe the plasma

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