Nuclear Power Engineering 2015 Issue 5 Review of Underground Nuclear Power Plant

Review of Underground Nuclear Power Plant
Niu Xinqiang;Luo Qi;Zhao Xin;Zhang Wenqi;Liu Haibo;Li Xiang;Changjiang Institute of Survey;Planning;Design and Research;Nuclear Power Institute of China;

..............page:1-5

Research on Key Technologies of Large-Scale Underground NPPs
Niu Xinqiang;Luo Qi;Zhao Xin;Zhang Wenqi;Liu Haibo;Li Xiang;Changjiang Institute of Survey;Planning;Design;and Research;Nuclear Power Institute of China;

..............page:6-11

Mechanical Calculation and Evaluation of Supports for Nuclear Power Plant Steam Generator
Xu Yu;Chu Qibao;Wang Qing;Liu Le;Wen Jing;Li Hailong;Nuclear and Radiation Safety Center;MEP;

..............page:12-14

Application of Two Response Spectrum Analysis Methods from RG1.92 for Steel Frame
Xu Shenghong;Liu Shenghua;Peng Xiaoping;Yang Shifeng;Shanghai Nuclear Engineering Research and Design Institute;

..............page:15-17

FEM Analysis for Dropping Test of Fresh Fuel Cask
Li Nan;Han Zhi;Wang Jun;Wang Kunpeng;Zhang Chunming;Yi Dayong;China Institute of Atomic Energy;Nuclear and Radiation Safety Center;MEP;

..............page:18-21

Evaluation Technology for Defects of Reactor Pressure Vessel Bolt Hole and Bolt
Zheng Liangang;Zou Mingzhong;Xie Hai;State Key Laboratory of Reactor System Design Technology;Nuclear Power Institute of China;

..............page:22-24

Optimal Analysis of Seismic Isolation of PCCS Water Storage Tank
Hou Gangling;Teng Fei;Jia Xiaofei;Song Tianshu;College of Aerospace and Civil Engineering;Harbin Engineering University;

..............page:25-29

Application of Nuclear Piping Calculation Program
Ning Qingkun;Chen Li;Tang Yujian;Tian Jinmei;China Nuclear Power Engineering CO.;Ltd.;

..............page:30-32

Seismic Analysis of Collection Tank for Middle Level Radioactive Waste Liquid
Jing Dan;Wang Jun;Dai Shoutong;Luan Lin;China Institute of Atomic Energy;

..............page:33-36

Experimental Study on Thick Rubber Bearings of Three-Dimensional Isolation of Nuclear Power Plants
Wang Tao;Li Jichao;Wang Fei;Institute of Engineering Mechanics;CEA;

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

Test and Research for Integrity Evaluation of Nuclear Pipe System under Seismic Effect
Zhang Shiwei;Shen Shuanquan;Liu Linlin;Xu Yugen;Li Xihua;Nuclear Power Institute of China;

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

Simple Method for Considering Soil-Structure Interaction in Three-Dimension Infinite Element Model of Nuclear Power Plant Building
Zhu Xiuyun;Qin Fan;Pan Rong;Li Jianbo;Nuclear and Radiation Safety Center;Ministry of Environmental Protection;School of Architecture & Civil Engineering;Liaocheng University;State Key Laboratory of Coastal and Offshore Engineering;Dalian University of Technology;

..............page:45-49

Contact Nonlinear Computation Method for Multi-Subassemblies Interaction in Fast Reactor Core
Gao Fuhai;Li Nan;China Institute of Atomic Energy;

..............page:50-53

Application of Multi-Point Response Spectrum Method in Seismic Analysis of Nuclear Power Equipment
Wang Yanping;Peng Xingming;Tang Yujian;China Nuclear Power Engineering CO.;LTD.;

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

Research on Vibration Characteristics Boundary Condition of Core Barrel of Nuclear Reactors
Tan Tiancai;Gao Lixia;Yu Danping;Ma Jianzhong;Reactor Engineering Research Institute;Nuclear Power Institute of China;

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

Implementation Evaluation of Small Flow Pipeline Vibration Transformation Plan for RIS System LHSI Pump
He Chao;Xi Zhide;Zhao Yue;Yuan Shaobo;Ma Jianzhong;Nuclear Power Institute of China;Hainan Nuclear Power Co.;Ltd;

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

Study on Dynamic Characteristics of Heat Transfer Tube in SG
Gao Lixia;Yu Danping;Tan Tiancai;Ma Jianzhong;Liu Litao;Nuclear Power Institute of China;

..............page:65-67

Vibration Control and Optimum Design of Piping System Based on Power Flow
Zhang Xiaoling;Liu Tianyan;Sun Lei;Zhang Kun;Qiao Hongwei;Lin Song;Nuclear Power Institute of China;

..............page:68-71

Validity Analysis of Rolled Plugs of Steam Generators Tube
Shi Shaobo;Shen Ping;Tian Xianglu;Gao Luyang;China Nuclear Power Operation Technology Corporation;LTD.;CNNP Nuclear power operations management Co.;Ltd.;

..............page:72-74

Numerical Simulation of Separation Efficiency and Pressure Drop of AP1000 Swirl-Vane Moisture Separator
Zhang Huang;Bo Hanliang;Chen Feng;Institute of Nuclear and New Energy Technology;Tsinghua University;

..............page:75-79

Vibration Analysis of Coupled Concentric Cylindrical Shells in Contact with an Annular Fluid Region
Dong Yu;Yang Yiren;Lu Li;School of Mechanics and Engineering;Southwest Jiaotong University;

..............page:80-82

Analysis of Relevant Problems of Shape Flow Resistance in Nuclear Power Plants
Yao Yangui;Shi Yang;Zhang Kai;Lu Mingchao;Shanghai Nuclear Engineering Research and Design Institute;

..............page:83-86

Random-Turbulence Excitation Research of Steam-Generator Inlet Tubes
Gao Lixia;Tan Tiancai;Yang Jie;Yu Danping;Ma Jianzhong;Nuclear Power Institute of China;

..............page:87-90

Research on Sloshing Characteristics in Passive Cooling Storage Tank of AP1000 under Long-Period Earthquake
Zeng Xiaojia;Lu Daogang;Dang Junjie;Liu Yu;Beijing Key Laboratory f Passive Safety Technology for Nuclear Energy;North China Electric Power University;China Nuclear Power Engineering Co.;Ltd.;

..............page:91-95

Application of Normalization Method to J-R Curve Testing of SA335 P11 Alloy Steel at Elevated Temperature
Zhang Xu;Pan Keqi;Liang Bingbing;Dou Yikang;Shanghai Nuclear Engineering Research and Design Institute;

..............page:96-100

FAT Iterative Method Based on Dual Conical Indentation to Obtain Properties of Materials
Chen Hui;Cai Lixun;Bao Chen;School of Mechanics and Engineering;Southwest Jiaotong University;

..............page:101-104

Research on Seismic Test of ACP1000 Control Rod Drive Line
Du Jianyong;Li Pengzhou;Li Qi;Liu Linlin;Xu Yugen;Li Tianyong;Ma Jianzhong;Qualification Center of Safety Classified Equipment of NPIC;

..............page:105-107

Assessment of 3# Primary Pump Vibration of Unit 1 in Qinshan NPP3
Yuan Shaobo;Chen Zhigao;Guo Longzhang;Huang Yongbo;Yu Danping;Cong Bing;He Chao;Liu Lingling;Nuclear Power Institute of China;CNNC Nuclear Power Operation Management CO.;LTD;

..............page:108-110

Improvement of Vibration Measurement for Nuclear-Class Pipes in Nuclear Power Plants during Decommissioning
Zhao Yue;He Chao;Xu Weizu;Wei Chao;Bao Yu;Hainan Nuclear Power Corporation;Nuclear Power Institute of China;

..............page:111-113

Fuel Assembly Model Test Based on SIMO
Xu Yugen;Liu Linlin;Wang Xu;Sun Lei;Nuclear Power Institute of China;

..............page:114-116

Study on End-Loading Qualification Test on Nuclear Class 1 Gate Valve and Notice
Xu Yugen;Wang Xu;Liu Linlin;Jiang Shenghan;Nuclear Power Institute of China;

..............page:117-119

Fracture Mechanics Analysis for Inlet Nozzle of RPV with Pipe Load Considered
Wang Dasheng;Liu Pan;Xiong Guangming;China Nuclear Power Design Co.;Ltd.;

..............page:120-123

Fatigue and Strength Analysis of CRF Pump with Flaw
Tan Xiaohui;Wang Wei;Luo Ting;Liu Zhiling;Chen Guangyi;Suzhou Nuclear Power Research Institute;Daya Bay Nuclear Power Operations and Management CO.;Ltd.;

..............page:124-127

Theory and Simulation Investigation on Crack Tip Blunting for Ductile Material
Pan Keqi;Zhang Xu;Shanghai Nuclear Engineering Research & Design Institute;

..............page:128-131

Probabilistic Analysis for Characteristic Values of Fracture Toughness
Li Yuebing;Gao Zengliang;Lei Yuebao;Institute of Process Equipment and Control Engineering;Zhejiang University of Technology;

..............page:132-135

Mechanic Problems in PWR Fuel Assembly Research and Development
Li Pengzhou;Li Qi;Nuclear Power Institute of China;

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

Analysis of A Large Commercial Aero Plane Crash on AP1000 Reinforced Concrete Shield Building
Cheng Shujian;Wang Xiaowen;Ge Honghui;Xia Zufeng;Huang Xiaolin;Shanghai Nuclear Engineering Research & Design Institute;

..............page:140-143

Mechanical Analysis for Personnel Air Lock in Third-Generation Nuclear Power Plants
Shi Ji;Xu Xiaogang;Yang Linmin;China Nuclear Power Engineering Co.Ltd.;

..............page:144-147

Effect of Tube Structural Style on Thermal Stress in CEFR Intermediate Heat Exchanger
Zhang Tianyi;Zhang Zhenxing;Hu Lina;Xu Yu;China Institute of Atomic Energy;Nuclear and Radiation Safety Center;

..............page:148-151

Stress Analysis and Structural Integrity Evaluation of Piping System in TMSR
Gong Wei;Zhang Xiaochun;Wang Xiao;Fu Yuan;Shanghai Institute of Applied Physics;Chinese Academy of Sciences;

..............page:152-155

Measurement and Analysis of Thermal Strain in Emergency Decay Heat Removal System in CEFR
Yu Huajin;Tang Long;Qi Min;Yu Danping;China Institute of Atomic Energy;Nuclear Power Institute of China;

..............page:156-160

Design of Alarm Software for NPP Virtual Control System
Dong Chenpeng;Leng Shan;Cheng Junjie;Southeast University;State Nuclear Power Automation System Engineering Company Ltd.;

..............page:161-164

PWR Power Distribution On-Line Monitoring Based on Harmonics Expansion Method
Li Zhuo;Wu Hongchun;Cao Liangzhi;Li Yunzhao;School of Nuclear Science and Technology in Xi’an Jiaotong University;

..............page:165-168

Experimental Study on Thermal Mixing in Emergency Core Cooling System
Ren Wuyue;Bian Jiawei;Yu Guojun;Tian Wenxi;Zhang Dalin;Su Guanghui;Qiu Suizheng;State Key laboratory of Multiphase Flow in Power Engineering Department of Nuclear Science and Technology;Xi’an Jiaotong University;Department of Nuclear Science and Technology;Xi’an Jiaotong University;

..............page:169-172

Study on Molten Fuel Fragmentation Behaviors Using Moving Particle Semi-Implicit Method
Zhang Rui;Tian Wenxi;Chen Ronghua;Su Guanghui;Qiu Suizheng;State Key Laboratory on Power Engineering and Multi-Phase Flow;Xi’an Jiaotong University;

..............page:173-177

Analysis of Characteristics for Liquid Entrainment through ADS-4 during a Small Break LOCA in AP1000
Wang Weiwei;Liu Lifang;Meng Zhaoming;Fu Xiaoliang;Tian Wenxi;Yang Yanhua;Su Guanghui;Qiu Suizheng;Department of Nuclear Science and Technology;Xi’an Jiaotong University;State Nuclear Power Software Development Center;National Energy Key Laboratory of Nuclear Power Software;

..............page:178-183

Numerical Simulation of Debris Bed Formation in Severe Accident
Zhang Bin;Wu Jian;M.Shamsuzzaman;Morita Koji;Shan Jianqiang;Chen Yaodong;Nuclear Science and Technology School;Xi’an Jiaotong University;China Nuclear Power Engineering Co.;Ltd.;Department of Applied Quantum Physics and Nuclear Engineering;Kyushu University;State Nuclear Power Research Institute;

..............page:184-186

Visual Experimental Investigation on Oscillations of Pressure Drop and Flow Rate of Two-Phase Flow in Mini-Channel
Chen Deqi;Wang Qinghua;Lu Qi;Pan Liangming;Key Laboratory of Low-Grade Energy Utilization Technologies and Systems;chongqing University;

..............page:187-193

Experiment Research on Corrosion Damage of Rubber O-Ring in High Temperature and High Pressure High CO₂ Environment
Zeng Dezhi;Li Tan;Zhou Zhiru;Zhang Zhi;Shi Taihe;Cui Qingwu;State Key Laboratory of Oil and Gas Reservoir Geology and Exploitation;Southwest Petroleum University;Changzhou Research Institute of Coating Chemical Co.Ltd;CNOOC;Nuclear Power Institute of China;No.1 Drilling Co.;Sinopec Zhongyuan Petroleum Engineering Co.Ltd;

..............page:194-198

Evaluation of Thermal Fatigue Life for SSRF High-Heat-Load Components
Xiao Weiling;Chen Haibo;Yin Yan;University of Science and technology of China;Department of Modern Mechanics;China Helicopter Design Research Institute;

..............page:199-203

Numerical Simulation of Hydraulically Expanded Tube-to-Tube Sheet Joints in Steam Generator
Ni Peng;Hui Hu;Wang Xiaodong;Lin Shaoxuan;Zhang Liyan;Chen Qingqi;MOE Key Laboratory of Safety Science of Pressurized System;East China University of Science and Technology;Nuclear Engineering Research and Design Institute;

..............page:204-207

Beryllium Localization and Verification Test of PHWR Fuel
Wang Wenli;CNNC Nuclear Power Operations Management Co.;Ltd;

..............page:208-210

Assessment of Mechanical Properties of Domestic A508-3 Steel
Yu Meifang;Luo Zhen;Zhao Yujin;School of Materials Science and Engineering;Tianjin University;

..............page:211-214