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	Feasibility analysis of method to avoid tube rupture in HTR-10 steam generator
	Jianling Dong ; Jiyang Fu ; Suyuan Yu ; Yang Meng
	2010-05-10 ; 2010-05-10
关键词	Practical/ crack detection fission reactor cooling fission reactor fuel fission reactor safety fracture nuclear reactor steam generators pipes/ tube rupture high temperature gas-cooled reactor steam generator HTR-10 steam generator tubes water flow graphite fuel elements graphite core fuel ball radioactivity primary loop pressure secondary loop helical tubes tube cracks eddy current detection volumetric in-service inspection leakage detection system operation loads SSE loads crack stability period reactor shutdown protection systems intratube pressure 10 MW/ A2844 Fission reactor protection systems, safety and accidents A2843B Cooling and heat recovery in fission reactors A2842D Fission reactor fuel elements A2850I Gas cooled reactors A6220M Fatigue, brittleness, fracture, and cracks A8140N Fatigue, embrittlement, and fracture B8220B Nuclear reactors/ power 1.0E+07 W
中文摘要	The 10MW high temperature gas-cooled reactor (HTR-10) steam generator tubing is the barrier between the primary loop and the secondary loop. Because the pressure of the primary side is less than that of the secondary side, the water and steam will flow into the primary loop if a tube ruptures and react with the graphite fuel elements and the graphite core internals which will result in destruction of the fuel ball, release of radioactivity into the primary loop and increased primary loop pressure. The HTR-10 steam generator tubes are helical tubes with small curvature radius so tube cracks cannot be detected by using eddy current detection for volumetric in-service inspection. This paper describes a leakage detection system and reasons that the crack whose leakage can be detected by the leakage detection system is stable for normal operation loads and SSE loads. Within the crack stability period, all protection actions of the reactor shutdown protection systems could be completed and the intra-tube pressure decreases to a safe level. [All rights reserved Elsevier].
语种	英语 ; 英语
出版者	Elsevier ; Netherlands
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/22751]
专题	清华大学
推荐引用方式 GB/T 7714	Jianling Dong,Jiyang Fu,Suyuan Yu,et al. Feasibility analysis of method to avoid tube rupture in HTR-10 steam generator[J],2010, 2010.
APA	Jianling Dong,Jiyang Fu,Suyuan Yu,&Yang Meng.(2010).Feasibility analysis of method to avoid tube rupture in HTR-10 steam generator..
MLA	Jianling Dong,et al."Feasibility analysis of method to avoid tube rupture in HTR-10 steam generator".(2010).

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