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西安交通大学 [9]

兰州理工大学 [2]

清华大学 [1]

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期刊论文 [9]

会议论文 [2]

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	Study on pressure surge characteristics of reactor coolant pump shaft stuck accident condition based on wavelet analysis 期刊论文 Nuclear Engineering and Design, 2022, 卷号: 397 作者: Qu, Zehui; Li, Yibin; Pan, Jun; Li, Donghao; Yang, Congxin 收藏 \| 浏览/下载：233/0 \| 提交时间：2022/09/22 Accidents Coolants Fluid structure interaction Impellers Pressure vessels Steam generators Timing circuits Vortex flow Wavelet analysis Closed systems Flow passage Guide-vane Pressure surges Primary circuits Pump shafts Reactor coolant pumps Reactor primary circuit closed system Shaft stick accident Wavelet-analysis
	Study on Hydraulic Characteristics of Reactor Coolant Pump Shutdown Transition Process Based on Primary Circuit Closed System 期刊论文 Frontiers in Energy Research, 2022, 卷号: 9 作者: Li, Dong-Hao; Li, Yi-Bin; Zhang, Fan; Guo, Yan-Lei; Yang, Cong-Xin 收藏 \| 浏览/下载：21/0 \| 提交时间：2022/04/21 Drops Electric network analysis Impellers Pressure vessels Pumps Steam generators Timing circuits Closed systems Hydraulic characteristic Primary circuits Process-based Reactor coolant pumps Reactor primary circuit closed system Shutdown Stable operation Structural characteristics Transition process
	Mathematical modeling of a pressurizer in a pressurized water reactor for control design 期刊论文 Applied Mathematical Modelling, 2019, 卷号: 65, 页码: 187-206 作者: Wang, Pengfei; He, Jianjun; Wei, Xinyu; Zhao, Fuyu 收藏 \| 浏览/下载：6/0 \| 提交时间：2019/11/19 Controller designs Controller performance Conventional proportional integrals Pressurizer Reactor coolant systems Satisfactory control Transfer function model Water level controllers
	Study on Optimization Method for Periodical Tests of CPR1000 Nuclear Power Unit 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 123-127 作者: Yang, Bo; Zhang, Zhao; Zhao, Fuyu; Shen, Rongfa 收藏 \| 浏览/下载：11/0 \| 提交时间：2019/11/19 Nuclear power unit Nuclear safety Optimization method Optimization scheme Periodic tests Reactor coolant systems Residual heat removal systems Safety analysis
	Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System 期刊论文 Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 067-070 作者: Wei, Shiying; Wang, Chenglong; Su, Guanghui; Tian, Wenxi; Qiu, Suizheng 收藏 \| 浏览/下载：14/0 \| 提交时间：2019/11/26 Cladding failures Coolant systems Direct contact boiling Lead-bismuth reactors Reactor systems Steady state and transients System safety Thermal hydraulics
	Experimental simulation analysis of ADS-4 entrainment and depressurization in AP1000 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 卷号: 50, 期号: [db:dc_citation_issue], 页码: 66-72 作者: Li, Pei-Ying; Xiang, Yan; Sun, Du-Cheng; Zhang, Da-Lin; Zhang, Peng 收藏 \| 浏览/下载：1/0 \| 提交时间：2019/12/02 Automatic depressurization systems Depressurizations Entrainment depositions Entrainment process Experimental conditions Experimental simulations Liquid entrainment Reactor coolant systems
	Experimental investigation of CCFL in pressurizer surge line with air-water 会议论文作者: Wang, Z. W.; Tian, W. X.; Yu, J. T.; Zhang, D. L.; Su, G. H. 收藏 \| 浏览/下载：5/0 \| 提交时间：2019/12/02 Automatic depressurization systems CCFL Counter-current flow limitation Experimental investigations Reactor Pressure Vessel Small break loss of coolant accidents Surge lines Visualization experiment
	Experimental and theoretical research on liquid entrainment in AP1000 ADS blow-down phase of SBLOCA 会议论文 - 收藏 \| 浏览/下载：2/0 \| 提交时间：2019/12/02 ADETEL AP1000 Automatic depressurization systems Determination methods Entrainment depositions Horizontal pipe flow Reactor coolant systems Theoretical research
	Analysis of cold leg small break LOCA for AP1000 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2011, 卷号: 45, 期号: [db:dc_citation_issue], 页码: 541-547 作者: Yang, Jiang; Tian, Wen-Xi; Su, Guang-Hui; Qiu, Sui-Zheng 收藏 \| 浏览/下载：3/0 \| 提交时间：2019/12/10 AP1000 Calculation results Cladding temperatures Passive core cooling systems Reactor coolant systems RELAP5 Small break loss of coolant accidents Transient parameter
	Liquid collapse level monitoring for nuclear reactors during loss of coolant accident 期刊论文 2010, 2010 Li Shengqiang; Bo Hanliang; Wang Wenran; Jiang Shengyao 收藏 \| 浏览/下载：6/0

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