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536

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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

15,615 commits to develop branch, last one 4 days ago

327

662

other

54

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

81 commits to master branch, last one a day ago

147

257

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

1,253 commits to master branch, last one 11 days ago

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42

other

3

Stochastic Calculator Of Neutron transport Equation

scone neutronics monte-carlo radiation-transport

Created 2022-07-06

1,193 commits to main branch, last one about a month ago

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40

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

3,675 commits to develop branch, last one a day ago