Computational Research on Nuclear Thermal Hydraulics and Severe Accident
| Title: |
Computational Research on Nuclear Thermal Hydraulics and Severe Accident |
| DNr: |
NAISS 2026/3-131 |
| Project Type: |
NAISS Medium |
| Principal Investigator: |
Pavel Kudinov <pkudinov@kth.se> |
| Affiliation: |
Kungliga Tekniska högskolan |
| Duration: |
2026-03-30 – 2027-04-01 |
| Classification: |
20306 20399 |
| Homepage: |
https://www.physics.kth.se/ne/sunrise |
| Keywords: |
|
Abstract
In this proposal we expect the resource can be used to complete the following projects,
1. We are continuing our research on CFD modelling of the flow accelerated corrosion/erosion process for the next generation nuclear reactor in Sweden under the umbrella of the SUNRISE project, which is funded by the Swedish Foundation for Strategic Research (SSF). We continue our research in LES analysis of the SEFACE facility on the new staggered hole configuration. In addition, the computational resources will be used to perform additional RANS and LES for flow structure equivalence comparision for the new high speed water mockup facility. Further RANS simulations are envisaged with the use of the resources on existing high temperature liquid Pb erosion facilities in our group.
2. We are continuing our research within several OECD/NEA projects. The motivation is to provide analytical support to experimental activities OECD/NEA PANDA, SSM ASOP, NKS PAS-SMR. The goal is to develop, validate and apply numerical methods for prediction of thermal-hydraulic phenomena of safety importance relevant to (i) the Pressure Suppression Pool (PSP), spray and mixing nozzles of the ultimate heat sink, etc.; (ii) transients in Small Modular Reactors (SMRs). The work will provide analytical support to the experiments in a large scale PANDA facility at PSI, Switzerland, HWAT facility at KTH, SEF-POOL and PPOOLEX facilities at the LUT, Finland. The project work will provide pre-test analysis to define test conditions and carry out post-test development and validation of the new models to improve predictive capabilities of the numerical tools used in safety analysis for Swedish nuclear power plants and different designs of SMRs.
3. As part of NKS-STATUS project, KTH is working on source term and uncertainty quantification in Nordic BWRs. Focusing on LOCA and SBO accident scenarios, KTH has performed large scale sensitivity and uncertainty analysis using MELCOR during phase 1,2,3. New pathways for source term release were identified, vis-a-vis basemat meltthrough. Quantification of uncertainties is ongoing, and requires computational resources. As part of the EU-SASPAM project, we are working on modelling severe accident progression in SMRs. We aim to conduct the EPZ assessment, incorporating advanced modelling of uncertainties, including both best-estimate and conservative analyses using MELCOR and MACCS system codes. Because MELCOR and MACCS modelling parameters contribute to uncertainties, accident scenarios add to splinters, sensitivity studies number in hundreds of MELCOR cases. The project intends to provide a safety analysis for SMRs in EU region, helping regulators, utilities and vendors in their decision making.