Openmc Python Packages

cad-to-dagmc

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

openbnct

Open, DICOM-native, transport-neutral BNCT research and independent-verification platform built in Rust, with an egui workbench and OpenMC first.

paramak

Create parametric 3D fusion reactor CAD and neutronics models

neutronics-material-maker

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

openmc-plasma-source

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

tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

matproplib

Materials that are dependent on conditions

openmc-plotter

Native plotting GUI for model design and verification

openmc-source-plotter

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

watts

Workflow and Template Toolkit for Simulation (WATTS)

stl-to-h5m

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

promptmc

Infrastructure for safely using OpenMC with LLMs

dagmc-bounding-box

Finds the bounding box and related properties of a DAGMC geometry

openmc-tally-unit-converter

A Python package that finds and converts OpenMC tally units.

openmc-cell-segmenter

Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.