Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
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Updated
Mar 19, 2021 - C#
Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
A high-fidelity, free user input cylinder meshing tool for MCNP.
Create parametric 3D fusion reactor CAD models
The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results
Combines open source packages to produce an automated fusion specific neutronics workflow
DIF3D plugin to the ARMI nuclear reactor analysis framework
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
An open source utility to convert various publicly available macroscopic nuclear cross section formats
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
Isotropic Monte Carlo simulations examining thermal neutron statistics in water, lead, and graphite, including animated neutron history, delta tracking and spherical geometry adaptations.
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
THOR is a radiation transport code for unstructured meshes.
Simple code to simulate Neutron Scattering in Non-Radiative matter using Monte Carlo simulations
Openmc-FEnicsx for muLtiphysics tutorIAl
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