Nuclear Power Engineering 2015 Issue 4 Experimental Study on Natural Circulation Characteristics of Passive Residual Heat Removal System

Experimental Study on Natural Circulation Characteristics of Passive Residual Heat Removal System
Xi Zhao;Xiong Wanyu;Xie Feng;Gong Houjun;Zhuo Wenbin;Li Pengzhou;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institute of China;

..............page:1-3

Flow Patterns Transition in Vertical and Upwardly Inclined Two-Phase Flow
Xie Tianzhou;Chen Bingde;Xu Jianjun;Bao Wei;CNNC Key Laboratory on Nuclear Reactor Thermo Hydraulics Technology;Nuclear Power Institute of China;

..............page:4-7

Theoretical Study on Effect of Flow Channel Local Inclination on Critical Heat Flux
Liu Wenxing;Peng Jinfeng;Xu Jianjun;Huang Yanping;Yang Zumao;CNNC Key Laboratory on Nuclear Reactor Thermal-hydraulics Technology;Nuclear Power Institute of China;

..............page:8-11

Experimental Study on Flow and Heat Transfer in an Equivalent Model for Sphere Bed
Du Daiquan;Zhou Huihui;Xu Jianjun;Yang Zumao;Huang Yanping;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;NPIC;

..............page:12-16

Effect of Liquid Viscosity on Film Interfacial Instability on the Wall of Cyclone Separator
Huang Zhen;Xiao Zejun;Yan Xiao;Zan Yuanfeng;Li Yong;Yuan Dewen;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institution of China;

..............page:17-22

Effect of the Structure of Steam Flow Limiter on Its Resistance and Flow Field Details
Yang Xuelong;Feng Jing;Zhang Qian;Wang Wei;Wang Xianyuan;China Nuclear Power Operation Technology Corporation LTD;Research Institute of Nuclear Power Operation;

..............page:23-27

Analysis and Improvement of Throttling Orifice of NPP RCV System
Zhao Jingxiong;Liu Changliang;China Nuclear Power Engineering Co.;Ltd.;

..............page:28-31

Preliminary Research on Design of Traveling Wave Reactor
Yan Mingyu;Chen Bin;Feng Linna;Zhang Yong;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:32-36

Fuel Management for VVER-1000 using PC Fuel
Xu Min;Wang Hongxia;Huo Xiaodong;Yi Xuan;Yu Yang;China Nuclear Power Engineering Co;

..............page:37-40

Development and Verification of Three Dimensional Code System for SCWR Core Steady State Analysis
Wang Lianjie;Zhao Wenbo;Yang Ping;Ma Yongqiang;Lu Di;Sun Wei;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:41-44

Suggested Corrections of Standard Response Spectrum in Code for Seismic Design of Nuclear Power Plants
Bai Wenting;Feng Guozhong;China Nuclear Power Engineering Co.;Ltd.;Hebei Branch;

..............page:45-48

Structural Integrity Assessment for RPV under Typical Event Transients
Zhu Guangqiang;Tian Xianglu;Wei Wenbin;Research Institute of Nuclear Power Operation;Equipment Research Department;Shandong Nuclear Power Co.Ltd;

..............page:49-53

Analysis of Optimization Requirements of Impact Test in Welding Procedure Qualification for Mechanical Components of Nuclear Islands
Wang Heng;Dong An;China Nuclear Power Engineering Cooperation Ltd.;

..............page:54-56

Test Study on Effect of Blocking Mass on Finite Plate Vibration Attenuation
Li Pengzhou;Lu Jun;Sun Lei;Reactor Engineering Sub-Institute;Nuclear Power Institute of China;

..............page:57-60

Load Analysis and Factors Determined Method of Special Lifting Device for NPP Nuclear Island Major Components
Weng Songfeng;Dong Zhengping;Science and Technology on Reactor System Design Technology laboratory;Nuclear Power Institute of China;

..............page:61-64

Development of Computer Code on Pipe Crack Leakage
Wu Wanjun;Xie Hai;Lan Bin;Huang Xuan;Ye Xianhui;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:65-68

Optimal Design of Pressure Control System of PWR Pressurizer Based on Digital Regulators
Qian Hong;Zhou Lei;Mao Lei;Shanghai University of Electric Power;Shanghai Nuclear Engineering Research & Design Institute;

..............page:69-73

Application of GASFLOW and COM3D in Analysis of Hydrogen Behavior of Nuclear Reactors
Zhang Ruidong;Sun Ximing;Dong Yujie;Tsinghua University;

..............page:74-78

Strategies of Factory Tests of Safety Digital Instrumentation and Control System in Nuclear Power Plants
Wang Zhongqiu;Wu Qi;Zhang Yunbo;Liu Le;Nuclear and Radiation Safety Center;MEP;

..............page:79-82

Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors
Xiao Jun;Chen Luyao;Fu Zhenghong;Qiu Shaoyu;Cheng Yong;Lin Zhenxia;Science and Technology on Reactor Fuel and Materials Laboratory;Nuclear Power Institute of China;School of Material Science and Engineering;Xihua University;

..............page:83-85

Effect of Coating Temperature on Density of Porous Pyrolytic Carbon
Tang Mingguo;Wu Shihong;Li Yingjie;Yang Jing;Science and Technology on Reactor Fuel and Materials Laboratory;Nuclear Power Institute of China;

..............page:86-89

Study on Compatibility of U-Mo Alloy and Zirconium Alloy
Liu Yunming;Chen Jiangang;Liu Chaohong;Sun Changlong;Pang Xiaoxuan;Wang Luquan;Yin Changgeng;Science and Technology on Reactor Fuel and Materials Laboratory;Nuclear Power Institute of China;China Academy of Engineering Physics;

..............page:90-94

Development of ZCU Water Levels Search Function of CANDU Reactor
Ju Haitao;Wu Hongchun;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power institute of China;Department of Nuclear Engineering;Xi’an Jiaotong University;

..............page:95-97

Experimental Investigation on Entrainment of Fourth Stage Automatic Depressurization System in AP1000
Xiang Yan;Sun Ducheng;Liu Jianchang;Wu yingwei;Zhang Peng;Qiu Suizheng;Su Guanghui;School of Nuclear Science and Technology;Xi’an Jiaotong University;State Nuclear Power Technology Research and Development Center;

..............page:98-102

Design Improvement of CRDM Nozzle for RPV
Wang Xiaobin;Li Yuguang;Luo Ying;Fang Caishun;Chen Haibo;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:103-106

Consideration of ALARA Principle in Design of Steam Generator
Cui Suwen;Ren Hongbing;Gao Xipei;China Nuclear Power Design Co.;Ltd.;

..............page:107-110

Analysis of Reactor Core Positioning Method for PWR Manipulator Crane
Liu Yiqing;Ma Lei;Yan Tingyu;Huaneng Shandong Shidao Bay Nuclear Power Plant;

..............page:111-114

Study on Improvement of Operation Parameters at Cement Solidification System
Yan Wenchao;Huang Wentao;Zeng Bin;Zhang Jingsong;Chen Yunming;Li Xingyi;Hong Yongxia;Nuclear Power Institute of China;

..............page:115-117

Calculations and Simulation of Ultrasonic Inaccessible Zones for Outlet to Shell Weld in RPV
Hong Maocheng;Yu Zhe;Lin Ge;Xiao Xuezhu;Ma Guanbing;CGNPC Inspection Technology Co.;Ltd;

..............page:118-121

Research on Judgement Method for Fuel Element Damages in HFETR
Chen Qibing;Li Ziyan;Yu Dejun;Nuclear Power Institute of China;

..............page:122-124

Maintenance Strategy Optimization Analysis for Circulating Water Pump in Daya Bay Nuclear Power Plant
Zhang Sheng;Wu Tao;Mo Chunni;Suzhou Nuclear Power Research Institute;Daya Bay Nuclear Power Operations and Management Co.;Ltd.;

..............page:125-129

Improvement of Replacement Scheme for RCP No.1 Cartridge Flange Screw in CPR1000 Nuclear Power Station
Wang Yuxu;Yue kai;Su Bin;China Nuclear Power Engineering Co.;Ltd;

..............page:130-132

Analysis and Solution of Unable Tripping Fault of Refueling Machine Gripper
Peng Feng;CNNC Nuclear Power Operations Management Co.;Ltd;

..............page:133-135

Safety Analysis of Spent Fuel Pool in Case of LOCA
Wang Haitao;Shan Jianqiang;Gou Junli;Zhang Bo;Nuclear Science and Technology School;Xi’an Jiaotong University;

..............page:136-139

Research on the Effect of Coupled Motions on Flow Instability Boundary
Ma Yingying;Qian Libo;Tian Wenxi;Su Guanghui;Qiu Suizheng;Huang Yanping;Yan Xiao;State Key Laboratory on Power Engineering and Multi-Phase Flow;Xi’an Jiaotong University;Nuclear Power Institute of China;

..............page:140-144

Study on Drop Performance Test of AP1000 Control Rod Drive Line
Gu Hanyang;Zhang Chaozhu;Chen Yuqing;Zhou Xiaojia;Liu Gang;School of Nuclear Science and Engineering;Shanghai Jiao Tong University;Shanghai Nuclear Engineering Research and Design Institute;

..............page:145-148

Safety Analysis of Loss of Cooling Accident for Typical Spent Fuel Pool
Zhang Zhongwei;Liang Guoxing;School of Nuclear Science and Engineering;Shanghai Jiao Tong University;

..............page:149-153

Study on Engineering Development for Monte Carlo Burnup Code
Qiang Shenglong;Yin Qiang;Liu Cong;Yao Dong;Song Danrong;Lu Wei;Liu Dong;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;CNOOC Research Center;

..............page:154-157

Numerical Simulation of Mixing Turbulent Flow in Rod Bundle with Spacer Grids
Wei Zonglan;Zhang Yu;Liu Songtao;Ma Qiang;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;CNOOC Research Center;

..............page:158-162