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510

786

other

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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

313

628

other

56

Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303

geometry shielding nuclear-data visualization hadron-physics medical-physics photon-transport neutron-transport particle-tracking particle-transport high-energy-physics radiation-transport scientific-computing computational-physics monte-carlo-simulation multiphysics-simulation high-performance-computing

Created 2016-06-21

80 commits to master branch, last one 15 days ago

146

247

agpl-3.0

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Toolkit for Monte Carlo simulation of ionizing radiation — Trousse d'outils logiciels pour la simulation Monte Carlo du rayonnement ionisant

egsnrc dosimetry metrology medical-physics radiation-therapy ionizing-radiation radiation-transport monte-carlo-simulation

Created 2012-11-28

1,175 commits to master branch, last one about a year ago

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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 2 months ago

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mit

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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