Openmc Python Packages

aleathor

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

cad-to-dagmc

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

neutronics-material-maker

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

matproplib

Materials that are dependent on conditions

tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

paramak

Create parametric 3D fusion reactor CAD and neutronics models

watts

Workflow and Template Toolkit for Simulation (WATTS)

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.

openmc-plasma-source

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

stl-to-h5m

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

openmc-tally-unit-converter

Convert OpenMC tallies into user friendly units

openmc-cell-segmenter

todo

dagmc-bounding-box

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