NUMERICAL STUDY ON THE CREEP STRAIN CHARACTERISTICS FOR TMSR REACTOR COOLANT PIPING UNDER THERMAL LOADING

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	NUMERICAL STUDY ON THE CREEP STRAIN CHARACTERISTICS FOR TMSR REACTOR COOLANT PIPING UNDER THERMAL LOADING
	Gong, W; Zhang, XC; Xie, MQ; Fu, Y; Wang, X
刊名	PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 6B
	2019
期号	-页码:—
文献子类	期刊论文
英文摘要	Safety assessment and economy design of piping system at high temperature is highly important in power and nuclear engineering. ASME-NH code considers cyclic failure modes at elevated temperature and provides the rules and damage limits for creep-fatigue interaction. Based on the calculation methods for creep strain increment of ASME-NH code, this paper investigated the creep-fatigue damage of reactor coolant piping in Thorium Molten Salt Reactor-Solid Fuel (TMSR-SFO) loop. By designing different stress cycles, the different creep strain increment and creep-fatigue assessments are systematically conducted. It was found that the creep strain increment of SF0 loop accumulated in one stress cycle time was higher than that accumulated during the entire service life divided by the number of stress cycles. Similarly, the creep-fatigue damage was also lower. And thus, an economical design method for SFO/SF1 loop was given.
语种	英语
内容类型	期刊论文
源URL	[http://ir.sinap.ac.cn/handle/331007/31735]
专题	上海应用物理研究所_中科院上海应用物理研究所2011-2017年
作者单位	Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
推荐引用方式 GB/T 7714	Gong, W,Zhang, XC,Xie, MQ,et al. NUMERICAL STUDY ON THE CREEP STRAIN CHARACTERISTICS FOR TMSR REACTOR COOLANT PIPING UNDER THERMAL LOADING[J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 6B,2019(-):—.
APA	Gong, W,Zhang, XC,Xie, MQ,Fu, Y,&Wang, X.(2019).NUMERICAL STUDY ON THE CREEP STRAIN CHARACTERISTICS FOR TMSR REACTOR COOLANT PIPING UNDER THERMAL LOADING.PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 6B(-),—.
MLA	Gong, W,et al."NUMERICAL STUDY ON THE CREEP STRAIN CHARACTERISTICS FOR TMSR REACTOR COOLANT PIPING UNDER THERMAL LOADING".PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 6B .-(2019):—.