5 results found Sort:

openmc-dev
openmc openmc-dev
503
774
other
71
OpenMC Monte Carlo Code
openmc neutronics nuclear-data nuclear-energy nuclear-fusion photon-transport neutron-transport particle-transport nuclear-engineering radiation-transport computational-physics monte-carlo-simulation high-performance-computing
Created 2011-07-21
15,522 commits to develop branch, last one 20 hours ago
fusion-energy
neutronics-workshop fusion-energy
53
125
mit
4
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
flux dagmc course energy fusion openmc nuclear photons tritium learning neutrons spectrum training tutorial neutronics simulations containerised
Created 2021-07-15
1,853 commits to main branch, last one 6 days ago
stellarmesh
stellarmesh stellarmesh
8
42
mit
2
Meshing library for nuclear workflows
gmsh moab dagmc openmc cadquery build123d neutronics opencascade monte-carlo-simulation
Created 2023-09-12
149 commits to main branch, last one 3 months ago
CambridgeNuclear
SCONE CambridgeNuclear
22
36
other
3
Stochastic Calculator Of Neutron transport Equation
scone neutronics monte-carlo radiation-transport
Created 2022-07-06
1,182 commits to main branch, last one about a month ago
idaholab
MontePy idaholab
7
32
mit
6
MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
api mcnp mcnp6 neutronics monte-carlo radiation-transport
Created 2024-01-09
3,546 commits to develop branch, last one 8 days ago