Abstract
This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOWTRANSURANUS. This tool is based on a semi-implicit depletion scheme with pin-by-pin feedback, mesh-based field exchange and an object-oriented software design. The impact of including fuel-performance capabilities is analyzed, with focus on high-burnup effects. The treatment of the Doppler feedback to the neutronics is examined as well, in particular the use of radial fuel-temperature profiles or radially averaged values.
| Original language | English |
|---|---|
| Pages (from-to) | 1033-1040 |
| Number of pages | 8 |
| Journal | EPJ Web of Conferences |
| Volume | 247 |
| DOIs | |
| Publication status | Published - 2020 |
| MoE publication type | A4 Article in a conference publication |
| Event | International Conference on Physics of Reactors, PHYSOR 2020: Transition to a Scalable Nuclear Future - Cambridge, United Kingdom Duration: 28 Mar 2020 → 2 Apr 2020 |
Funding
This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-W?rttemberg and DFG (?Deutsche Forschungsgemeinschaft?). This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097, and was performed on the computational resource ForHLR II funded by the Ministry of Science, Research and the Arts Baden-Württemberg and DFG (”Deutsche Forschungsgemeinschaft”).
Keywords
- Multiphysics
- PWR
- Serpent2
- SUBCHANFLOW
- TRANSURANUS