Neutronics Python Packages

cad-to-dagmc

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

montepy

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

matproplib

Materials that are dependent on conditions

tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

brep-part-finder

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

mcnp-input-reader

The package for reading mcnp input in a pythonic way

stl-to-h5m

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

spectrum-plotter

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

mcdc

MC/DC (Monte Carlo Dynamic Code): a performant, scalable, and machine-portable Python-based Monte Carlo neutron transport package

vertices-to-h5m

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

regular-mesh-plotter

A Python package for creating publication quality plots of regular mesh tallies with the underlying geometry

openmc-regular-mesh-plotter

A Python package for creating plots of OpenMC regular mesh tallies with the underlying geometry