openmc topic
openmc
OpenMC Monte Carlo Code
openmc_mcnp_adapter
Tool for converting MCNP input files to OpenMC classes/XML
plotter
Native plotting GUI for model design and verification
openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
paramak
Create parametric 3D fusion reactor CAD and neutronics models
neutronics_material_maker
A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
watts
Workflow and Template Toolkit for Simulation (WATTS)
enrico
ENRICO: Exascale Nuclear Reactor Investigative COde
stellarmesh
Meshing library for nuclear workflows