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Wang H, Villanueva W. Structural behavior of an ablated reactor pressure vessel wall with external cooling. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104446] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/31/2022]
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Yu P, Ma W. Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103874] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Wang H, Villanueva W, Chen Y, Kulachenko A, Bechta S. Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111196] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Structural integrity assessment of Calandria of 540 MWe PHWR for in-vessel corium retention. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110791] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Kuang B, Liu P, Wang F, Cao K, Zhang K. Influences of some engineered factors on IVR-ERVC limits. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.03.016] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Mao J, Bao S, Lu Z, Luo L, Gao Z. The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2018. [DOI: 10.1115/1.4040494] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
The so-called in-vessel retention (IVR) was considered as a severe accident management strategy and had been certified by Nuclear Regulatory Commission (NRC) in U.S. as a standard measure for severe accident management since 1996. In the core meltdown accident, the reactor pressure vessel (RPV) integrity should be ensured during the prescribed time of 72 h. However, in traditional concept of IVR, several factors that affect the RPV failure were not considered in the structural safety assessment, including the effect of corium crust on the RPV failure. Actually, the crust strength is of significant importance in the context of a severe reactor accident in which molten core material melts through the reactor vessel and collects on the lower head (LH) of the RPV. Consequently, the RPV integrity is significantly influenced by the crust. A strong, coherent crust anchored to the RPV walls could allow the yet-molten corium to fall away from the crust as it erodes the RPV, therefore thermally decoupling the melt pool from the coolant and sharply reducing the cooling rate. Due to the thermal resistance of the crust layer, it somewhat prevents further attack of melt pool from the RPV. In the present study, the effect of crust on RPV structural behaviors was examined under multilayered crust formation conditions with consideration of detailed thermal characteristics, such as high-temperature gradient across the wall thickness. Thereafter, systematic finite element analyses and subsequent damage evaluation with varying parameters were performed on a representative RPV to figure out the possibility of high temperature induced failures with the effect of crust layer.
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Affiliation(s)
- Jianfeng Mao
- Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou 310032, China; Engineering Research Center of Process Equipment and Re-manufacturing, Ministry of Education, Hangzhou 310014, China e-mail:
| | - Shiyi Bao
- Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou 310032, China e-mail:
| | - Zhiming Lu
- Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou 310032, China e-mail:
| | - Lijia Luo
- Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou 310032, China e-mail:
| | - Zengliang Gao
- Institute of Process Equipment and Control Engineering, Zhejiang University of Technology, Hangzhou 310032, China; Engineering Research Center of Process Equipment and Re-manufacturing, Ministry of Education, Hangzhou 310014, China e-mail:
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Loktionov V, Mukhtarov E, Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.12.018] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Loktionov V, Mukhtarov E, Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accident. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.11.015] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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The influence of the crust layer on RPV structural failure under severe accident condition. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.02.033] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Jianfeng M, Xiangqing L, Shiyi B, Lijia L, Zengliang G. Investigation on multilayer failure mechanism of RPV with a high temperature gradient from core meltdown scenario. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.10.005] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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