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A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
Created 2021-07-15
1,885 commits to main branch, last one 3 days ago
Meshing library for nuclear workflows
Created 2023-09-12
157 commits to main branch, last one 2 months ago
Stochastic Calculator Of Neutron transport Equation
Created 2022-07-06
1,193 commits to main branch, last one 23 days ago
MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
Created 2024-01-09
3,642 commits to develop branch, last one 8 days ago