A nodalization study on modeling the containment and reactor pool of an integral PWR
• Nodalization study of containment and reactor pool of an iPWR with MELCOR 2.2. • Single-volume models provided similar accident progression as detailed nodalization. • Detailed nodalization provided slightly lower containment pressures in DBA scenario. • Effect of nodalization on fission product release was small. This study investigates the impact of nodalization of the containment and reactor pool of a small integral Pressurized Water Reactor (iPWR) using the MELCOR 2.2 code. The research focuses on Design 1 of the EU-funded SASPAM-SA project, featuring a containment partially submerged in the reactor pool. Two accident scenarios were analyzed: a Design Basis Accident (DBA) and a severe accident. The simulations were conducted with four different nodalizations: a detailed base model, a single-volume containment model, a single-volume pool model, and a single-volume model for both the containment and the pool. The results indicate that while detailed nodalization can simulate temperature stratification, its effect on the overall accident simulation results, pressures and fission product releases is limited. The findings suggest that differences between single-volume and more detailed nodalizations are relatively small, with the detailed nodalization providing slightly lower containment pressures during the DBA scenario due to more efficient heat transfer.
Authors
- Tuomo Sevón (ORCID: https://orcid.org/0000-0001-9041-380X)
Institutions
- VTT Technical Research Centre of Finland (FI)
Publication Details
- Journal
- Annals of Nuclear Energy
- Published
- 2025-09-09
- DOI
- https://doi.org/10.1016/j.anucene.2025.111866
- Citations
- 1
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 0.52