CAP1400 IVR related design features and assessment

Shi, Guobao; Gu, Peiwen; Lu, Wei; Wang, Jiayun; Cao, Kemei; Zhang, Kun; Guo, Ning

doi:10.1016/j.nucengdes.2019.03.002

Cited by 17 publications

(2 citation statements)

References 8 publications

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“…This design is the largest Generation III PWR. Ensuring its advanced nature from the very beginning; CAP1400 comprehensively inherits the philosophy of the passive concept and the simplification of AP1000 [44][45][46].…”

Section: State Nuclear Power Technology Corporation Pwr Designmentioning

confidence: 99%

A Global Review of PWR Nuclear Power Plants

2020

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Nuclear energy is presented as a real option in the face of the current problem of climate change and the need to reduce CO2 emissions. The nuclear reactor design with the greatest global impact throughout history and which has the most ambitious development plans is the Pressurized Water Reactor (PWR). Thus, a global review of such a reactor design is presented in this paper, utilizing the analysis of (i) technical aspects of the different variants of the PWR design implemented over the past eight years, (ii) the level of implementation of PWR nuclear power plants in the world, and (iii) a life extension scenario and future trends in PWR design based on current research and development (R&D) activity. To develop the second analysis, a statistical study of the implementation of the different PWR variants has been carried out. Such a statistical analysis is based on the operating factor, which represents the relative frequency of reactors operating around the world. The results reflect the hegemony of the western variants in the 300 reactors currently operating, highlighting the North American and French versions. Furthermore, a simulation of a possible scenario of increasing the useful life of operational PWRs up to 60 years has been proposed, seeing that in 2050 the generation capacity of nuclear PWRs power plants will decrease by 50%, and the number of operating reactors by 70%.

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Section: State Nuclear Power Technology Corporation Pwr Designmentioning

confidence: 99%

A Global Review of PWR Nuclear Power Plants

2020

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“…Due to high reliability and low construction difficulty, the concept of IVR-ERVC is widely employed in the GEN-III and GEN-II+ pressurized water reactors (PWRs), including AP600/ 1000 (Zhang et al, 2010), APR1400 (Oh and Kim, 2005), VVER1000/320 (Sangiorgi and Ezzidi, 2015), and CAP1400 (Shi et al, 2019). The key principle of the IVR-ERVC strategy lies in that the external cooling water is quickly injected into the reactor pit through active or passive means after severe accidents, forming a natural circulation in the annular flow channel.…”

Section: Introductionmentioning

confidence: 99%

Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment

Chen

Zhan

et al. 2022

Front. Energy Res.

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Due to large uncertainty, the effectiveness of in-vessel retention (IVR) with external reactor vessel cooling (ERVC) for high-power reactors cannot be fully demonstrated during the transient process. To optimize the current IVR-ERVC strategy, the concept of IVR-ERVC with in-vessel injection (IVI) is studied. Two feasible IVI designs are proposed: 1) using the passive IVR water tank to implement simultaneous water injection in-vessel and ex-vessel and 2) using the passive severe accident dedicated in-vessel injection tanks (SADITs) to implement water injection in-vessel. The research on the feasibility and effectiveness of IVI is performed, and the corresponding negative effects are analyzed. The calculation results by using MIDAC show that the two proposed IVI concepts can greatly delay the accident progression in the core and reduce the decay heat peak of the molten pool in the lower head, thereby improving the effectiveness of the current IVR-ERVC strategy. And the negative effects are within acceptable ranges.

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