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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October 2018
Research-Article
The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
Jianfeng Mao,
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: maojianfeng@zjut.edu.cn
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: maojianfeng@zjut.edu.cn
Search for other works by this author on:
Shiyi Bao,
Shiyi Bao
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: bsy@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: bsy@zjut.edu.cn
Search for other works by this author on:
Zhiming Lu,
Zhiming Lu
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lzm@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lzm@zjut.edu.cn
Search for other works by this author on:
Lijia Luo,
Lijia Luo
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lijialuo@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lijialuo@zjut.edu.cn
Search for other works by this author on:
Zengliang Gao
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: zlgao@zjut.edu.cn
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: zlgao@zjut.edu.cn
Search for other works by this author on:
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: maojianfeng@zjut.edu.cn
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: maojianfeng@zjut.edu.cn
Shiyi Bao
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: bsy@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: bsy@zjut.edu.cn
Zhiming Lu
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lzm@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lzm@zjut.edu.cn
Lijia Luo
Institute of Process Equipment and
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lijialuo@zjut.edu.cn
Control Engineering,
Zhejiang University of Technology,
Hangzhou 310032, China
e-mail: lijialuo@zjut.edu.cn
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: zlgao@zjut.edu.cn
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: zlgao@zjut.edu.cn
1Corresponding author.
Manuscript received October 30, 2017; final manuscript received April 23, 2018; published online September 10, 2018. Assoc. Editor: Tomio Okawa.
ASME J of Nuclear Rad Sci. Oct 2018, 4(4): 041015 (9 pages)
Published Online: September 10, 2018
Article history
Received:
October 30, 2017
Revised:
April 23, 2018
Citation
Mao, J., Bao, S., Lu, Z., Luo, L., and Gao, Z. (September 10, 2018). "The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident." ASME. ASME J of Nuclear Rad Sci. October 2018; 4(4): 041015. https://doi.org/10.1115/1.4040494
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