Neutronics 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

montepy

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

brep-part-finder

A Python package to identify the part ID number in Brep format CAD files

openmc-regular-mesh-plotter

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

mcnp-input-reader

The package for reading mcnp input in a pythonic way

stl-to-h5m

Converts STL files to a DAGMC h5m file using PyMoab

regular-mesh-plotter

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

vertices-to-h5m

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

spectrum-plotter

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

paramak-neutronics

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