neutronics topic
openmc
OpenMC Monte Carlo Code
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 models
stellarmesh
Meshing library for nuclear workflows
SCONE
Stochastic Calculator Of Neutron transport Equation
MontePy
MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
MCDC
MC/DC: Monte Carlo Dynamic Code
openmc-ecosystem
List of open source projects related to OpenMC