I am calculating neutron heating of components in a 3D tomamak geometry. I used both MCNP and OpenMC to obtain the values but they don’t match. I tried used simple reduced order model ( cylinders ) to see if the problem was in the geometry and still numbers are off. Materials are exactly same using FENDL3.2b. I am still not sure what could be the problem. Any thoughts?
Related Topics
| Topic | Replies | Views | Activity | |
|---|---|---|---|---|
| Verification of OpenMC TBR evaluation using MCNP as reference | 2 | 334 | October 20, 2023 | |
| Inelastic Scattering and data reading bugs/issues | 5 | 253 | January 31, 2014 | |
| Neutron flux and reaction rates discrepancies with MCNP | 2 | 305 | January 19, 2024 | |
| Keff results significantly different from MCNP | 3 | 669 | January 6, 2020 | |
| Data.njoy.make_ace_thermal problem | 0 | 249 | February 22, 2023 |