2021核动力工程Requires access

Study on Function Extension of Pressurizer Fast Depressurization System for Gen III PWR NPPs

Jiajia Zhang, Deng Wei, Jun Xiao, Gong Yu

Open publisher page 1 citations

Abstract

A nuclear power plant of Gen Ⅲ pressurized water reactor (PWR) in China has installed the pressurizer fast depressurization system for fast depressurization of the primary loop under severe accidents. With respect to this NPP, according to the general method and process of applying the probabilistic safety assessment (PSA) to the NPP design improvement, this study, focusing on the improvement plan of extending the pressurizer fast depressurization system function to the primary feed & bleed for depressurization to enable the use of this system as a standby pressure relief measure for the pressurizer safety valve, performs the PSA modeling and the feasibility evaluation and demonstration. Finally, this study shows that the improvement plan can reduce the core damage frequency of a NPP greatly, without any new negative effect, so the plan is feasible and can be implemented. Consequently, the NPPs should fully tap the potential of existing system equipment to further improve the safety and economical efficiency of NPPs.

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What this paper is about

A nuclear power plant of Gen Ⅲ pressurized water reactor (PWR) in China has installed the pressurizer fast depressurization system for fast depressurization of the primary loop under severe accidents. With respect to this NPP, according to the general method and process of applying the probabilistic safety assessment (PSA) to the NPP design improvement, this study, focusing on the improvement plan of extending the pressurizer fast depressurization system function to the primary feed & bleed for depressurization to enable the use of this system as a standby pressure relief measure for the pressurizer safety valve, performs the PSA modeling and the feasibility evaluation and demonstration. Finally, this study shows that the improvement plan can reduce the core damage frequency of a NPP greatly, without any new negative effect, so the plan is feasible and can be implemented. Consequently, the NPPs should fully tap the potential of existing system equipment to further improve the safety and economical efficiency of NPPs.

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Available abstract

A nuclear power plant of Gen Ⅲ pressurized water reactor (PWR) in China has installed the pressurizer fast depressurization system for fast depressurization of the primary loop under severe accidents. With respect to this NPP, according to the general method and process of applying the probabilistic safety assessment (PSA) to the NPP design improvement, this study, focusing on the improvement plan of extending the pressurizer fast depressurization system function to the primary feed & bleed for depressurization to enable the use of this system as a standby pressure relief measure for the pressurizer safety valve, performs the PSA modeling and the feasibility evaluation and demonstration. Finally, this study shows that the improvement plan can reduce the core damage frequency of a NPP greatly, without any new negative effect, so the plan is feasible and can be implemented. Consequently, the NPPs should fully tap the potential of existing system equipment to further improve the safety and economical efficiency of NPPs.

Key concepts: Pressurizer, Cabin pressurization, Safety valve, Pressurized water reactor, Nuclear power plant, Relief valve, Nuclear engineering, System safety

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