Effect of Elevated Temperature and Internal Pressure due to Severe Accidents on the Internal Pressure Capacity of Prestressed Concrete Containment Vessel

Author:

Lee Sangwoo1ORCID,Cho Woo-Min2ORCID,Son Hoyoung1,Woo Han-Sang2,Ju Bu-Seog1ORCID,Chang Yoon-Suk2ORCID

Affiliation:

1. Department of Civil Engineering, Kyung Hee University, Yongin-si, Gyeonggi-do, 17104, Republic of Korea

2. Department of Nuclear Engineering, Kyung Hee University, Yongin-si, Gyeonggi-do, 17104, Republic of Korea

Abstract

The integrity of containment buildings in nuclear power plants is crucial for preventing the release of radioactive materials during severe accidents. This study investigates the effect of the uncertainty in temperature-dependent strength of concrete on the internal pressure capacity of prestressed concrete containment vessel (PCCV). To this end, a high-fidelity finite element model is developed and the uncertainty in concrete material properties due to temperature variations is taken into account for a finite element analysis with internal pressure and temperature histories. In addition, two limit states of PCCV, such as onset of leakage and functional failure, are defined to investigate internal pressure capacity depending on the different damages to PCCV. The results provide insights into the behavior of PCCV under severe accident conditions and the impact of the uncertainty in the concrete material due to temperature on their performance, in terms of the leakage of PCCV. This research enhances the understanding of PCCV’s response to internal pressure and temperature and contributes to the safety assessment of nuclear power plants.

Funder

Nuclear Safety and Security Commission

Publisher

Hindawi Limited

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

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