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Openmc Python Packages

Python packages with the GitHub topic openmc. Sorted by relevance, with stars and monthly downloads.
giovanni-mariano
aleathor

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

13K 2 0
fusion-energy
cad-to-dagmc

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

8K 54 11
fusion-energy
neutronics-material-maker

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

3K 27 12
Fusion-Power-Plant-Framework
matproplib

Materials that are dependent on conditions

1K 3 0
Fusion-Power-Plant-Framework
tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

1K 7 3
fusion-energy
paramak

Create parametric 3D fusion reactor CAD and neutronics models

1K 96 29
watts-dev
watts

Workflow and Template Toolkit for Simulation (WATTS)

901 37 23
openmc-dev
openmc-plotter

Native plotting GUI for model design and verification

529 70 21
fusion-energy
openmc-source-plotter

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

482 13 7
fusion-energy
openmc-plasma-source

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

459 41 14
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.

387 3 2
fusion-energy
openmc-tally-unit-converter

Convert OpenMC tallies into user friendly units

273 7 2
fusion-energy
openmc-cell-segmenter

todo

239 3 0
fusion-energy
dagmc-bounding-box

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

223 0 2
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