| Name | Version | Summary | date |
| geouned |
1.5.0 |
Conversion tool from CAD to CGS/CGS to CAD for Monte Carlo particle transport codes (OpenMC, Phits, Serpent, MCNP) |
2024-12-12 17:41:02 |
| paramak |
0.9.5 |
Create 3D fusion reactor CAD models based on input parameters |
2024-10-16 06:19:58 |
| neutronics-material-maker |
1.2.1 |
A tool for making reproducible materials and standardizing use across several neutronics codes |
2024-10-01 13:55:27 |
| openmc-source-plotter |
0.7.1 |
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles. |
2024-05-10 21:37:05 |
| openmc-regular-mesh-plotter |
1.2.2 |
A Python package for creating plots of OpenMC regular mesh tallies with the underlying geometry |
2024-05-09 09:55:43 |
| openmc-plasma-source |
0.3.1 |
Creates tokamak and ICF plasma sources for OpenMC |
2024-04-13 22:39:08 |
| openmc-cylindrical-mesh-plotter |
0.3.3 |
A Python package for creating plots of OpenMC cylindrical mesh tallies |
2024-03-20 22:38:46 |