Openmc Python Packages

cad-to-dagmc

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

promptmc

Infrastructure for safely using OpenMC with LLMs

matproplib

Materials that are dependent on conditions

tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

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

paramak

Create parametric 3D fusion reactor CAD and neutronics models

openmc-source-plotter

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

aleathor

Python library for debugging Constructive Solid Geometry (CSG) models for MCNP and OpenMC

openmc-plotter

Native plotting GUI for model design and verification

watts

Workflow and Template Toolkit for Simulation

stl-to-h5m

Converts STL files to a DAGMC h5m file using PyMoab

openmc-cell-segmenter

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

openmc-tally-unit-converter

Convert OpenMC tallies into user friendly units

dagmc-bounding-box

Find the bounding box and other related properties of a DAGMC h5m file

paramak-neutronics

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