Computational Research on Nuclear Thermal Hydraulics
Title: Computational Research on Nuclear Thermal Hydraulics
DNr: NAISS 2023/5-456
Project Type: NAISS Medium Compute
Principal Investigator: Pavel Kudinov <>
Affiliation: Kungliga Tekniska högskolan
Duration: 2023-12-21 – 2025-01-01
Classification: 20306


We present a medium-level request for NAISS HPC resources. In this proposal we would like to include the following scientific projects for the resoruces allocation, 1. We are continuing our research within the SUNRISE (Sustainable Nuclear Energy Research In Sweden) project to explore an effective modeling approach for the flow-accelerated corrosion / erosion (FACE) phenomenon in heavy liquid metal (Work Package 5). We have used wall-modeled large eddy simulation (WMLES) in our experimental facility, SEFACE, and were able to successfully simulate and collect important flow statistics to support both the design of the facility and the scientific investigation. We plan to extend the WMLES work to other test chambers for rotating disk turbulent flows and; we intend to use our own developed scalar wall model to conduct both RANS and WMLES simulations with dissolution process on a representative experimental corrosion test facilities. This would enable us to conduct the first investigation on the effect of intermittent turbulence dynamics and the roughness transition on dissolution behavior. The outcome of such works pave the way for future extension to couple solid diffusion and oxidation behaviour in transient mode. Also, we will use the latest data format version of OpenFOAM to generate DNS snapshots on a range of Re and Pr to prepare for machine learning research tasks. 2. We are continuing our research within several OECD/NEA projects. The motivation is to provide analytical support to experimental activities OECD/NEA PANDA and THEMIS, EU McSAFER,. 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) under prototypic conditions including steam injection and condensation, activation of different systems such as spray and mixing nozzles of the ultimate heat sink, aerosol retention and transport 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 Lappeenranta-Lahti University of Technology. 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.