Passive nuclear power plants emphasize the “In vessel retention” idea such that, after a postulated severe accident event, the reactor vessel wall, flooded with emergency cooling water, will maintain its structural integrity and consequently keep the molten core inside the reactor vessel. However, steam explosion may still occur when the melting core or molten metal is mixed with cooling water. The huge pressure pulses from the steam explosion may be a threat to the structural integrity of the reactor vessel lower head and the potential failure may make the situation difficult to control. This paper presents a detailed analysis on the structural integrity of a reactor vessel lower head. First, a mathematical model is built to relate the equivalent plastic strain in the lower head under explosive loads based on the law of conservation of energy. Then a finite element model, using the computer code ABAQUS, is built and the material’s yield strength as a function of strain rate was simulated using the Bodner-Symonds methodology. With this model, the dynamic response and the structural integrity of the reactor vessel lower head is studied, considering the effect of the magnitude, the shape and the duration of the pressure pulses. The method used in this paper is believed to be applicable to other types of devices containing potential explosive materials and thus could provide guiding significance to similar problems.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5583-6
PROCEEDINGS PAPER
Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads
Guohong Xue,
Guohong Xue
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Yinbiao He,
Yinbiao He
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Ming Cao,
Ming Cao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Hao Yu,
Hao Yu
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Yongjian Gao
Yongjian Gao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Search for other works by this author on:
Guohong Xue
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Yinbiao He
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Ming Cao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Hao Yu
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Yongjian Gao
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Paper No:
ICONE21-15831, V006T15A013; 8 pages
Published Online:
February 7, 2014
Citation
Xue, G, He, Y, Cao, M, Yu, H, & Gao, Y. "Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 6: Beyond Design Basis Events; Student Paper Competition. Chengdu, China. July 29–August 2, 2013. V006T15A013. ASME. https://doi.org/10.1115/ICONE21-15831
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