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Neutronics Python Packages

Python packages with the GitHub topic neutronics. Sorted by monthly downloads, with stars and forks.
fusion-energy
cad-to-dagmc

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

10K 63 15
idaholab
montepy

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

2K 66 30
tannhorn
morana

Python reference implementation for finite-volume neutron-diffusion calculations on regular hex-z lattices

780 5 0
Fusion-Power-Plant-Framework
tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

711 8 4
Fusion-Power-Plant-Framework
matproplib

Materials that are dependent on conditions

711 4 2
ENEA-Fusion-Neutronics
mcnp-input-reader

The package for reading mcnp input in a pythonic way

502 8 4
fusion-energy
brep-part-finder

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

404 0 0
fusion-energy
stl-to-h5m

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

293 3 2
fusion-energy
spectrum-plotter

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

286 4 0
fusion-energy
regular-mesh-plotter

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

255 16 1
fusion-energy
openmc-regular-mesh-plotter

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

254 16 1
rjonace
promptmc

Infrastructure for safely using OpenMC with LLMs

218 2 1
fusion-energy
vertices-to-h5m

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

192 3 3
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