OpenMC Monte Carlo Code
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Updated
Jun 13, 2024 - Python
OpenMC Monte Carlo Code
Create DAGMC geometry from CAD
MontePy is a Python library (API) to read, edit, and write MCNP input files.
MC/DC: Monte Carlo Dynamic Code
Combines open source packages to produce an automated fusion specific neutronics workflow
A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.
DIF3D plugin to the ARMI nuclear reactor analysis framework
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
The package for reading mcnp input in a pythonic way
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results
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