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

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...

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Bibliographic Details
Published in:International journal of energy research 2024-01, Vol.2024, p.1-16
Main Authors: Lee, Sangwoo, Cho, Woo-Min, Son, Hoyoung, Woo, Han-Sang, Ju, Bu-Seog, Chang, Yoon-Suk
Format: Article
Language:English
Subjects:
Accident conditions
Accidents
Concrete
Containment
Containment vessels
Finite element method
High temperature
Internal pressure
Leakage
Limit states
Material properties
Nuclear accidents & safety
Nuclear power plants
Nuclear reactor containment
Nuclear safety
Pressure
Prestressed concrete
Radioactive materials
Temperature
Temperature dependence
Tendons
Uncertainty
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Summary: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.
ISSN:0363-907X
1099-114X
DOI:10.1155/2024/9717587