Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Pretest analysis of a prestressed concrete containment 1:3.2 scale model under thermal-pressure coupling conditions

  • Qingyu Yang (Key Lab of Structures Dynamic Behavior and Control of the Ministry of Education, Harbin Institute of Technology) ;
  • Jiachuan Yan (Key Lab of Structures Dynamic Behavior and Control of the Ministry of Education, Harbin Institute of Technology) ;
  • Feng Fan (Key Lab of Structures Dynamic Behavior and Control of the Ministry of Education, Harbin Institute of Technology)
  • Received : 2022.09.08
  • Accepted : 2023.03.01
  • Published : 2023.06.25
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Abstract

In nuclear power plant (NPP) accidents, the containment is subject to high temperatures and high internal pressures, which may further trigger serious chain accidents such as core meltdown and hydrogen explosion, resulting in a significantly higher accident level. Therefore, studying the mechanical performance of a containment under high temperature and high internal pressure is relevant to the safety of NPPs. Based on similarity principles, the 1:3.2 scale model of a prestressed concrete containment vessel (PCCV) of a NPP was designed. The loading method, which considers the thermal-pressure coupling conditions, was used. The mechanical response of the PCCV was investigated with a simultaneous increase in internal pressure and temperature, and the failure mechanism of the PCCV under thermal-pressure coupling conditions was revealed.

Keywords

Acknowledgement

This work was supported by the National Key Research and Development Project of China [No. 2020YFB1901403]; the National Natural Science Foundation of China [No. 52178127]; the Natural Science Foundation of Heilongjiang Province of China [No. LH2021E072]; the Fundamental Research Funds for the Central Universities of China [No. HIT.NSRIF202233].

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