Atomic Energy Science and Technology 2008 Issue z2 Three-Dimensional Numerical Simulation of Secondary Side Flow Field in Steam Generator

Three-Dimensional Numerical Simulation of Secondary Side Flow Field in Steam Generator
JIANG Xing;ZHANG Ming;XIE Yong-cheng;YAO Wei-da

..............page:438-443

Impact of Irradiation-Induced Deformation for Nuclear Graphite on Irradiation-induced Stress and Life
WANG Hai-tao;YU Su-yuan

..............page:630-633

Fatigue Evaluation of Pressurizer Surge Line Concerning Thermal Stratification Effect
LIANG Bing-bing;LI Gang;WANG Gao-yang

..............page:448-453

Nozzle Loads Optimization Analysis of Outflow Primary Loop Piping in China Advanced Research Reactor
DAI Shou-tong;WANG Jun;HAN Zhi

..............page:490-494

Stability Analysis on Plate-Type Structure Based on Incompressible Viscous Flow
LU Li;YANG Yi-ren

..............page:454-457

Seismic Analysis of Containment With Hemisphere Dome for Advanced Nuclear Power Plant
WANG Ming-dan;LING Yun;WANG Xiao-wen;XIA Zu-feng

..............page:401-406

Research on Nonlinear Seismic Analytical Method of Reactor Coolant System
ZHANG Yi-xiong;JIANG Nai-bin;AI Hong-lei;WANG Wei

..............page:407-410

yuan zi neng ke xue ji shu zheng gao jian ze

..............page:封底

Sealing Characteristic Analysis for Unusual Sealing Structure
CAO Ming;HE Yin-biao;ZHANG Wan-ping;HUANG Qing

..............page:707-710

Design of Calibration Apparatus of High Temperature Strain Gauge
LIU Zi-cai;LU Yan-yan;HE Cheng-yi

..............page:704-706

Technological Characteristics, Design and Mechanics Analysis of Main Technology System and Equipment for China Experimental Fast Reactor
YU Hua-jin;LI Wen-hong;WANG Bing;YANG Hong-yi;LIU Jia-yi

..............page:484-489

Design and FEM Analysis of Magnetic Joint in Self-actuated Shutdown System of Fast Neutron Reactor
SHANG Chang-zhong;LU Dao-gang

..............page:726-728

Crack Tip Field of Mode Ⅱ Interface of Film/Substrate System for Components of Nuclear Safety
LIU Zhi-wei;ZHANG Yong;LI Xi-hua

..............page:676-680

Three Dimensional Numerical Simulation of Decay Heat Scattering Out of Pent Fuel Storage Modular
JIANG Xing;YAO Yan-gui;XIE Yong-cheng;XU Shou-lv;YAO Wei-da

..............page:477-483

Investigation of Load Monitoring for Pterygoid Cantilever Plate Based on Fiber Bragg Gratings
JIANG Zhong-hua;HUANG Guo-jun

..............page:721-725

Analysis and Evaluation of Leak of Refueling Water Storage Tank Bottom Plate for Daya Bay Nuclear Power Station
LU Yue-chuan;WU Wan-jun;ZANG Feng-gang;SUN Ying-xue;LIU Wen-jin

..............page:648-651

Numerical Simulation for Sloshing Response of Free Surface in Main Vessel of Fast Reactor by Earthquake
WEI Yuan-yuan;LU Dao-gang;LIANG Ya-ping

..............page:472-476

Application of Numerical Analysis in Securing Shield Installation for China Experimental Fast Reactor
LI Nan;JIN Feng-lei;WANG Ming-zheng;SONG Qing

..............page:567-570

Determination of Unbalance Load in Rotor Dynamics Analysis for Magnetic Bearing System
XU Yang;WANG Hong-tao;YU Su-yuan;PAN Lu-lu

..............page:571-575

Influence on Stress of Lower Assembly With Different Steam Generator Partition Plates Simplification
JIN Ting

..............page:694-699

Nonlinear Finite Element Analysis for Out-of-Tolerance Holes Expansion in Tube Sheet of Steam Generator
CHEN Yin-qiang;ZHANG Shu-zhi;GUI Chun;LIU Hong-yun;WANG Xian-yuan

..............page:552-555

Stress and Fatigue Analysis for Outlet Nozzle of Nuclear Reactor Pressure Vessel
YANG Wen;ZHENG Lian-gang;YANG Yu

..............page:505-508

Method of Calculating Added Mass for Seismic Analysis of Fuel Assembly in Fast Breeder Reactor
WANG Wan-hui;LU Dao-gang

..............page:602-608

Dynamic Fracture Initiation Toughness Computation of Crack in Pipe Welding Field Under Impact Loading
WU Yun-gang;LI Peng-zhou;XU Ze-jian;LI Yu-long

..............page:661-663

Seismic Test Research of Control Rod Drive Line for China Experimental Fast Reactor
SUN Lei;YANG Hong-yi;CHEN Xue-de;SONG Qing;LI Tian-yong;LI Xi-hua;LI Peng-zhou;WEN Jing

..............page:422-425

Seismic Analysis and Stress Assessment of LOT150B-2 Water Cooling Unit in Ling\'ao Phase-2 Nuclear Power Plant
CUI Cheng-xin

..............page:411-413

Fracture Analysis for Flaw on Reactor Pressure Vessel Outlet Nozzle
ZHENG Bin;SUN Ying-xue;ZANG Feng-gang;LU Yue-chuan;YANG Yu;ZHENG Lian-gang;ZOU Ming-zhong

..............page:641-644

Seismic Analysis of Uranium Liquid Critical Facility
DAI Shou-tong;LIU Zhen-hua;ZHU Qing-fu;HAN Zhi;WANG Jun

..............page:426-430

Class 1 Piping Stress Analysis for CPR1000 Nuclear Power Plant
LIU Lang;ZHANG Zhou-hong;WU Gao-feng;FAN Li-ming

..............page:500-504

Consideration About Static and Dynamic Seismic Test for Nuclear Safety Class Equipment
FANG Qing-xian

..............page:609-611

Finite Element Analysis for Flange-Bolt of Nuclear Pressure Vessel
LIU Xin

..............page:556-561

Numerical Simulation for Distribution Header and Throttle Structure in China Experimental Fast Reactor
FENG Yu-heng;HU Wen-jun;QIAO Xue-dong;HOU Zhi-feng

..............page:463-467

Analysis for Fast Fracture of Cylinder Section Outside Reactor Core
LU Yue-chuan

..............page:612-614

Natural Vibration Analysis of Tube Bundle in Steam Generator
LI Yue-zhong;HAN Liang-bi;WANG Bai-song

..............page:458-462

Calculation Method for Flow Induced Vibration in Weak Coupled System
XI Zhi-de;CHEN Bing-de;LI Peng-zhou

..............page:444-447

Structure Characteristic of Auxiliary Bearing for HTR-10GT
YANG Guo-jun;SHI Zhen-gang;QIN Qing-quan;YU Su-yuan

..............page:685-688

Safety Analysis of Fuel Assemblies Transport by Train
LI Hai-long

..............page:700-703

Flaws Analysis and Safety Evaluation of Dissimilar Metal Weld Joints
HUANG Qing;HE Yin-biao;YAO Wei-da;XIE Yong-cheng

..............page:664-668

Intensity Analysis and Assessment for Reinforced Concrete Rooms of China Experimental Fast Reactor
WANG Lu-bo;LI Xiao-xuan

..............page:516-519

Seismic Analysis for Discharging Heat Exchanger of Chemical and Volume Control System
ZHANG Shi-wei

..............page:431-433

Development of V2MB Used to Linearize Stress Results From VENUS
WEN Jing;YANG Hong-yi;YU Hong;WANG Ming-zheng

..............page:562-566

Design and Analysis on Supporting Structure of Thermal Insulation Layer in HTR-PM Steam Generator
ZHANG Li;HE Shu-yan;WU Xin-xin;LIU Jun-jie

..............page:512-515

Analysis on Flow to Each of Unaffected Steam Generators of 900 MWe Pressurized-Water Reactor in Event of One Feed Water Line Break
ZHANG Xu-yao

..............page:434-437

Finite Element Analysis of Control Rod Drive Mechanism Housing Interference Fit
XIONG Guang-ming

..............page:580-583

Analysis of Electromagnetic Field for Direct Action Solenoid Valve With Structure Changing
LIU Qian-feng;BO Han-liang;QIN Ben-ke

..............page:689-693

Mechanics Performance of Typical Dissimilar-Material Threaded Fasteners Subjected to Preload and Cyclic Thermal Loads
ZHANG Ke-feng;XIE Yong-cheng;LIANG Xing-yun;YANG Ren-an

..............page:715-720

Numerical Analysis of Transfer and Purge Chamber for China Experimental Fast Reactor
LI Nan;GU Ji-pin

..............page:509-511

Experimental Study on Flow Induced Vibration of Heat Transfer Helical Tube Bundle
GAO Li-xia;JIANG Zi-long;MA Jian-zhong;LI Song;CONG Bin

..............page:468-471

Load Analysis and Stress Evaluation for Irradiation Surveillance Capsules and Supporting Structures in C-1 Modified Project
HUANG Qing;HE Yin-biao;ZHANG Ming;YAO Wei-da

..............page:528-531

Stress Analysis on Some Pipes of Emergency Decay Heat Removal System for China Experimental Fast Reactor
TANG Long;QI Min;YU Hua-jin

..............page:532-534

Reactor Vessel Stress Analysis for CPR1000 Nuclear Power Plant
WANG Jun-wei;ZHANG Zhou-hong;WU Gao-feng;FAN Li-ming

..............page:495-499

Stress Analysis and Assessment for Measurable Part of Variable Area Flowmeter
LI Hai-long;LUO Shi-yu;LI Xiao-xuan;WANG Lu-bo

..............page:524-527

Study of Strength and Plugging Criteria for Inconel 690 Steam Generator Tubes With Flaw
HUI Hu;LI Pei-ning;TANG Yi;NIE Yong;LIU Hong-yun;LI Si-yuan

..............page:634-640

Analysis Technology for Weld Residual Stress
SUN Ying-xue;LU Yue-chuan;ZANG Feng-gang

..............page:593-596

Mechanics Analysis and Assessment of Volume Control Tank
LI Song;SUN Lei;MA Jian-zhong;HU Yong-tao

..............page:414-417

Application in Pre-load Approach of Bolts Based on Initial Strain Theory to Stress Analysis
ZHAO Fei-yun;XU Ding-geng;HE Yin-biao

..............page:548-551

Design Seismic Response Spectrum Used in Design of Nuclear Facilities
PAN Rong

..............page:622-629

Development of Aging Management Program for Reactor Pressure Vessel on Nuclear Power Plant
XIE Yong-cheng;XU Xue-lian;DOU Yi-kang;HE Yin-biao

..............page:673-675

Effect of Piping Layout on Aseismatic Performance of Reactor Coolant System
AI Hong-lei;LIU Wen-jin

..............page:397-400

Treatment Technology of Reactor Pressure Vessel and Steam Generator Non Conformance
ZHENG Lian-gang;YANG Yu;ZANG Feng-gang

..............page:645-647

Stress Analysis and Evaluation of Internal Structures for China Experimental Fast Reactor
ZHANG Ming;HE Yin-biao;YAO Wei-da;XU Ding-geng;XIE Yong-cheng

..............page:543-547

Safety Review on Welding Defect Incident of In-Service Nuclear Auxiliary System Pipings
SUN Zao-zhan;WANG Qing;FANG Yong-gang

..............page:669-672

Preliminary Mechanical Analysis of Relay Frame\'s Reconstructed Support of Daya Bay Nuclear Power Station
ZHANG Xiao-ling;SUN Lei;LI Tian-yong;LI Xi-hua

..............page:520-523

Critical Speed Analysis of Active Magnetic Bearing-Test Rotor for HTR-10GT
WANG Hong-tao;SUN Li-bin;YU Su-yuan

..............page:576-579

Fatigue Analysis and Assessments of Flawed Welds for Auxiliary Piping of Reactor Coolant System
ZANG Feng-gang;WANG Wei;LIU Wen-jin;ZHANG Yi-xiong;ZENG Zhong-xiu;YANG Kai;ZOU Ming-zhong

..............page:618-621

Development of Flaw Assessment Technology Based on Applicability Principle
QI Min;WANG Yue-ying;YU Hua-jin;TANG Long

..............page:656-660

Free Drop Analysis of Transportation Package for Heavy Water
LI Xiao-xuan;WEN Jing;LI Hai-long

..............page:418-421

Effect Caused by Support Gap to Seismic Analysis for Secondary Piping
WU Wan-jun;LIU Wen-jin

..............page:597-601

Seismic Analysis and Strength Evaluation for AI25-1.055 Fan
XU Jing;SUN Lei;LI Xi-hua

..............page:535-538

Mechanical Behavior Analysis in Study of 60 a Design Life for Reactor Pressure Vessel
DU Juan;SUN Ying-xue;LU Yue-chuan

..............page:652-655

Stress Analysis and Evaluation for Screw Fasteners in Reactor Internals
WANG Chi-hu;LIANG Xing-yun;XIE Yong-cheng;YANG Ren-an

..............page:539-542

Thirty Years of Chinese Structural Mechanics in Reactor Technology
LI Peng-zhou

..............page:385-393

Experiment Study for Flow-Induced Vibration and Flow-Distribution on Full Scale Core of China Advanced Research Reactor
YU Dan-ping;JIANG Xian-guo;ZHANG Jian-wei;YANG Jie;MA Jian-zhong;HU Yong-tao

..............page:711-714

Reasons and Measures to Eliminate Operating-Basis Earthquake in Advanced Light Water Reactor Nuclear Power Plant
YAO Wei-da;ZHANG Ming;XIE Yong-cheng;SHEN Xiao-yao;QIAN Hao

..............page:615-617

Effects of Material Property on Reactor Pressure Vessel Structure Integrity During Pressurized Thermal Shock Events
CAO Ming;HE Yin-biao;ZHANG Wan-ping;HUANG Qing

..............page:588-592

New Development of Strain Gauge Measurement Technique and Applications in Reactor Structures etc. Engineerings
SHEN Guan-lin

..............page:681-684

Dynamic Constitutive Study for Visoelastic Damping Material
LIN Song;GAO Qing

..............page:584-587

Seismic Analysis and Qualification for Bent Structure of Iodine Absorber LSJH-31-1 Used in Nuclear Power Plant
LI Qi;SUN Lei;LI Xi-hua;HU Yong-tao

..............page:394-396