CFD Applications to Pressurized Thermal Shock-Related Phenomena

Yuria Okagaki*, Takashi Hibiki*, Yasuteru Sibamoto

*Corresponding author for this work

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

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Abstract

In pressurized water reactor accident scenarios, the injection of water from the emergency core cooling system (ECCS) (ECC injection) might induce a pressurized thermal shock (PTS), affecting the reactor pressure vessel (RPV) integrity. Therefore, PTS is a vital research issue in reactor safety, and its analysis is essential for evaluating the integrity of RPVs, which determines the reactor life. The PTS analysis comprises a coupled analysis between thermal-hydraulic and structural analyses. The thermal-hydraulic approach is particularly crucial, and reliable computational fluid dynamic (CFD) simulations should play a vital role in the future because predicting the temperature gradient of the RPV wall requires data on the transient temperature distribution of the downcomer (DC). Since one-dimensional codes cannot predict the complex three-dimensional flow features during ECC injection, PTS is one reactor safety issue where CFD simulation can benefit from complement evaluations with thermal-hydraulic system analysis codes. This study reviewed from the viewpoint of the turbulence models most affecting PTS analysis based on papers published since 2010 on single- and two-phase flow CFD simulation for the experiment on PTS performed in the Rossendorf coolant mixing model (ROCOM), transient two-phase flow (TOPFLOW), upper plenum test facility (UPTF), and large-scale test facility (LSTF). The results revealed that in single-phase flow CFD simulation, where knowledge and experience are sufficient, various turbulence models have been considered, and many analyses using large eddy simulation (LES) have been reported. For two-phase flow analysis of air-water conditions, interface capturing/tracking methods were used in addition to two-fluid models. The standard k - ϵ and shear stress transport (SST) ω models were still in the validated phase, and various turbulence models have yet to be fully validated. In the two-phase flow analysis of steam-water conditions, many studies have used two-fluid models and Reynolds-averaged Navier-Stoke (RANS), and NEPTUNE_CFD, in particular, has been reported to show excellent prediction performance based on years of accumulated validation. © 2024 Yuria Okagaki et al.
Original languageEnglish
Article number5114542
JournalInternational Journal of Energy Research
Volume2024
Online published24 Apr 2024
DOIs
Publication statusPublished - 2024

Funding

This work was performed under the contract research entrusted by the Secretariat of Nuclear Regulation Authority (NRA), Japan. The authors would like to thank Dr. T. Takeda and Mr. K. Hiyama of JAEA for providing the literature on LSTF and a window person on software for supercomputers, respectively, Dr. S. Abe of NRA for providing the knowledge on CFD simulation for PTS, CEA/DM2S/STMF/LMSF; Dr. M.G. Rodio of CEA for providing the study opportunity on TOPFLOW-PTS and NEPTUNE_CFD cord; Dr. S. You of ANSYS Japan K.K. for answering the questions on software; and Dr. T. Watanabe of former Fukui University for providing the literature and experiment information. One of the authors (T. Hibiki) appreciates the support through a Global STEM Professorship in Hong Kong and the Hong Kong Jockey Club.

Publisher's Copyright Statement

  • This full text is made available under CC-BY 4.0. https://creativecommons.org/licenses/by/4.0/

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