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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

15,529 commits to develop branch, last one 5 days ago

53

127

mit

6

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 about a month ago

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45

mit

2

Meshing library for nuclear workflows

gmsh moab dagmc openmc cadquery build123d neutronics opencascade monte-carlo-simulation

Created 2023-09-12

157 commits to main branch, last one 29 days ago

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38

other

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Stochastic Calculator Of Neutron transport Equation

scone neutronics monte-carlo radiation-transport

Created 2022-07-06

1,182 commits to main branch, last one 2 months ago

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34

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

3,616 commits to develop branch, last one 2 days ago