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Vol.9 No.2previous AASP17 (125-126-127-128-129-130-131-132-133-134-135-136-137-138-139-140-141-142) NT85

Academic Articles
Regular Paper Vol.9 No.2 (2017) p.84 - p.90

3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading

Xiaoyong Ruan1,*, Toshiki Nakasuji1 and Kazunori Morishita2

1 Graduate School of Energy Science, Kyoto University, Gokasho, Uji, Kyoto, 611-0011, Japan
2 Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto, 611-0011, Japan

Reactor Pressure Vessel (RPV) during Pressurized Thermal Shock (PTS) loading is a critical issue in assessing the safety of nuclear power plants. The most severe situation takes places during Emergency Core Cooling Systems (ECCS) cold water injection in the cold legs due to a Loss-Of-Coolant Accident (LOCA). Conventionally, one-dimensional thermal hydraulic analysis has been performed as well as the simple model fracture mechanics analysis. In the present study, the three-dimensional Computational Fluid Dynamics (CFD) simulation and a comprehensive fracture mechanics analysis are performed. A reference design of a four-loop RPV is applied, and three different cases of the mass flow rates are considered in the analysis. Based on temperature distribution obtained by CFD, the fracture mechanics analysis were carried out to investigate the structural integrity, where submodeling technique is employed. Our results indicate that the worst crack location is identified and the dependence of Stress Intensity Factor (SIF) on the position of RPV is clarified. It is useful information to inspect and maintain the RPV integrity.
Reactor Pressure Vessel, Pressurized Thermal Shocks, 3D-CFD, Fracture Mechanics, Stress Intensity Factor
Full Paper: PDF
Article Information
Article history:
Received 12 October 2016
Accepted 29 May 2017