Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition

doi:10.13832/j.jnpe.2024.01.0201

	Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition
其他题名	华龙一号主泵卡轴事故工况瞬态过渡过程数值分析
	Pan, Jun 1; Li, Yibin1,2 ; Qu, Zehui 1; Guo, Yanlei1,2 ; Yang, Congxin1,2 ; Wang, Xiuyong1,2
	2024-02
发表期刊	Hedongli Gongcheng/Nuclear Power Engineering
ISSN	0258-0926
卷号	45 期号:1 页码:201-209
摘要	In order to reveal the pipeline transient mechanism under the shaft jamming accident condition of the reactor coolant pump (RCP), a simplified fluid domain model of the coolant system of the three-loop reactor was established by matching the relationship between the resistance characteristics of the reactor coolant pump and the pipeline of the primary system. Based on the computational fluid dynamics (CFD) method, the actual transient flow process and the real-time change rule of parameters in the reactor coolant system under shaft jamming accident condition were reproduced, and the accident safety evaluation method of reactor coolant system under shaft jamming accident condition was established. The transient changes of main pipeline pressure, wall load of transition bend and pressure of three typical heat transfer tubes with radius of curvature were analyzed under shaft jamming accident condition. The results show that: in the process of the shaft jamming accident, the flow in the accident loop decreases to 0 m3/h and then increases in reverse, and reverse flow occurs. The pressure and wall load of the accident loop and other loops will change dramatically after the shaft jamming accident, and the change degree of the accident loop is greater. The pressure oscillation law of the heat transfer tubes with different curvature radii is basically the same, and the peak pressure of the monitoring point increases gradually along the direction from the inlet to the outlet of each heat transfer tube. © 2024 Atomic Energy Press. All rights reserved.
关键词	Accidents Coolants Heat transfer Oscillating flow Pipelines Pumps Transient analysis Accident conditions Fluid domain Heat-transfer tubes Pipeline transient mechanism Pipeline transients Pump shafts Reactor coolant pumps Reactor coolant systems Shaft jamming accident Transient process
DOI	10.13832/j.jnpe.2024.01.0201
收录类别	EI
语种	中文
出版者	Atomic Energy Press
EI入藏号	20240915644911
EI主题词	Computational fluid dynamics
EI分类号	618.2 Pumps ; 619.1 Pipe, Piping and Pipelines ; 631.1 Fluid Flow, General ; 641.2 Heat Transfer ; 723.5 Computer Applications ; 803 Chemical Agents and Basic Industrial Chemicals ; 914.1 Accidents and Accident Prevention ; 931.1 Mechanics
原始文献类型	Journal article (JA)
引用统计	无
文献类型	期刊论文
条目标识符	https://ir.lut.edu.cn/handle/2XXMBERH/169979
专题	能源与动力工程学院
通讯作者	Li, Yibin
作者单位	1.School of Energy and Power Engineering, Lanzhou University of Technology, Lanzhou; 730050, China; 2.Key Laboratory of Advanced Pumps, Valves and Fluid Control System, The Ministry of Education, Lanzhou University of Technology, Lanzhou; 730050, China
第一作者单位	新能源学院
通讯作者单位	新能源学院; 兰州理工大学
第一作者的第一单位	新能源学院
推荐引用方式 GB/T 7714	Pan, Jun,Li, Yibin,Qu, Zehui,et al. Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition[J]. Hedongli Gongcheng/Nuclear Power Engineering,2024,45(1):201-209.
APA	Pan, Jun,Li, Yibin,Qu, Zehui,Guo, Yanlei,Yang, Congxin,&Wang, Xiuyong.(2024).Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition.Hedongli Gongcheng/Nuclear Power Engineering,45(1),201-209.
MLA	Pan, Jun,et al."Numerical Analysis of Transient Process of HPR1000 Reactor Coolant Pump Shaft Jamming Accident Condition".Hedongli Gongcheng/Nuclear Power Engineering 45.1(2024):201-209.