Nuclear Techniques 2013 Issue 4 FRS comparative analysis of the nuclear power plant considering SSI effect

FRS comparative analysis of the nuclear power plant considering SSI effect
ZHU Xiuyun1 PAN Rong1;2 LI Jianbo 3 1 2 3

..............page:50-57

Research and project practice in AP1000 nuclear plant MCR assemblies seismic test
MA Yuanrui ZHU Yizhou WANG Chihu XIE Yongcheng

..............page:58-61

Stress analysis and evaluation of improved second-generation nuclear power plant piping systems
NING Qingkun TIAN Jinmei

..............page:62-66

Verification of FEM in AP1000 main control room seismic qualification
ZHU Yizhou MA Yuanrui XIE Yongcheng

..............page:67-71

Experimental study on seismic qualification test of AP1000 main control room equipment
LI Qi DU Jianyong LIU Linlin LI Tianyong

..............page:72-75

Time history analysis method for spent fuel racks
LI Chen1 QIAN Hao1 ZHANG Kai1 XIE Yongcheng2 XU Dinggeng1 1 2

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

Comparative study on seismic calculation method between response spectrum and time history analysis
ZHANG Qinghong1 JIN Ting2 SHANG Ertao2 1 2

..............page:8-13

Seismic analysis of steam generator and parameter sensitivity studies
QIAN Hao XU Dinggeng YANG Ren’an LIANG Xingyun

..............page:14-19

Seismic research on graphite reactor core
LAI Shigang SUN Libin ZHANG Zhengming

..............page:20-28

Research of model simplifying and seismic analysis for electric heaters of the pressurizer
YANG Nengren XU Xiao LIU Pan

..............page:29-31

Sealing behavior simulation technology research for CPR1000 reactor pressure vessel
XIONG Guangming DENG Xiaoyun DUAN Yuangang JIN Ting

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

Research on control rod drive mechanism seismic test acceptance criteria
LIU Gang WANG Feng ZHANG Yanglie XIE Yongcheng

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

Reactor internals and hold down spring stiffness/reaction calculation
ZHANG Zhai XUE Guohong

..............page:41-45

Design floor response spectra calculation rearch for 18-5 critical device building
HUANG Wenhui CHEN Xuede

..............page:46-49

Study on non-linear analysis technology of reactor internals core barrel alignment plate
ZHU Kun CHEN Huiliang YU Hao

..............page:242-245

Stress analysis of passive hydrogen autocatalytic recombiner
TANG Yujian NING Qingkun GONG Zhenbang LIU Shubin

..............page:246-250

Finite element analysis of the flange sealing structure in the reactor system
LI Yuan HE Yinbiao LIAO Jianhui HUANG Qing SHEN Rui

..............page:251-255

Research progress and recommendations on reactor pressure vessel integrity under hypothetical core melt down accident
YAO Yangui NING Dong WU Zhiwei CAO Ming XIE Yongcheng HE Yinbiao YAO Weida

..............page:76-81

Analysis on the fluid and structure interaction in the control rod drop process
LI Peng1 LIU Tong2 ZHOU Yuemin2 YANG Yiren1 LU Li1 GUO Yan2 1 2

..............page:82-86

Influence of steam generator tube gaps on the dynamic characteristics of tubes
ZHANG Kai

..............page:87-92

Development of leak rate calculation model and code in piping
YIN Haifeng LIANG Bingbing XU Ning

..............page:93-96

Research on crack-opening displacement and leak rate prediction of the through-wall crack in LBB design
QIAO Hongwei LI Qi LIU Zhiwei LI Xihua

..............page:97-103

Simulation of AP1000 reactor coolant pump flow field CFD
XIA Shuan1 FENG Bin1 ZHANG Haijun2 1 2

..............page:104-110

Numerical study on the valve acoustic resonance behaviors
ZU Hongbiao ZHANG Kai

..............page:111-115

Research on acoustic fatigue experimental models of the dryer in steam generators
LI Qi1 ZHANG Kai2 ZU Hongbiao2 1 2

..............page:116-119

Study on lifting of large structure module in AP1000 nuclear power plant
ZUO Shaobing CHU Yanchun YE Zhiyan

..............page:339-342

Drop impact analysis method of radioactive material container
LI Hailong SUN Zaozhan SUN Shuhai XU Yu

..............page:343-346

Research on thermal and mechanical behaviour of a Freeze-Valve for molten salt reactor
LI Qiming TANG Zhongfeng FU Yuan WANG Naxiu

..............page:256-264

Analysis of temperature field of direct action solenoid valve
LIU Qianfeng BO Hanliang WANG Luo

..............page:265-269

Influence of the Taylor vortex on heat transfer of the flow in gaps
QIN Jie

..............page:120-124

CAP1000 integrated head package airflow system fluid field analysis
YU Hao ZHANG Ming FENG Shaodong HAO Guofeng WENG Yu

..............page:125-128

Calculation and evaluation mythology of the flawed pipe and the compute program development
LIU Chang1 LIANG Xingyun2 QIAN Hao1 YAO Weida1 1 2

..............page:129-133

Fracture assessment for reactor pressure vessel flaw
ZHENG Bin

..............page:134-137

Initial plastic failure analysis for nuclear pipeline with internal surface crack
LI Tieping ZHANG Chunming MA Shuai

..............page:138-141

Local fracture behavior in an Alloy 52M dissimilar metal welded joint in nuclear power plants
WANG Haitao WANG Guozhen XUAN Fuzhen TU Shandong LIU Changjun

..............page:142-147

Research on structural integral assessment of cylinders with circumference cracks under pressurized thermal shock based on probabilistic fracture mechanics
LI Yuebing JIN Weiya BAO Shiyi GAO Zengliang LEI Yuebao

..............page:148-153

Structure integrity evaluation of AP1000 RPV under PTS
WANG Donghui ZHANG Yaping ZHONG Zhimin LI Kai ZHANG Jing

..............page:154-161

Influence on off-center TWC on LBB applicability
LIANG Bingbing SHI Wang LI Gang

..............page:162-166

Stepping movement analysis of control rod drive mechanism
XU Yantao ZU Hongbiao

..............page:347-351

Analysis of effect to reactor cavity structure by steam explosion outside the reactor
GOU Hongliang

..............page:352-354

Dynamic analysis of the DN350 squib valve shear cap
ZHOU Shaochong

..............page:355-359

Acoustic-structure coupling scaling laws for model test based steam dryer acoustic fatigue derivations
ZHANG Kai

..............page:360-366

Off-center crack growth analysis of inner-surface crack pipe
QI Tao

..............page:167-172

Calculation research of fracture mechanics parameters KJ of cracks in elbows
ZHOU Jiyun1 ZHANG Wei2 LUAN Xingfeng2 ZHU Guangqiang1 1 2

..............page:173-178

Probability fracture mechanics analysis of plates with surface cracks
ZHAO Lei LI Yuebing LEI Yuebao GAO Zengliang

..............page:179-184

Remaining strength assessment methodology of cylindrical tubing containing local wall thinning defect
TANG Yi1 WANG Qi2 SUN Haitao3 LI Pingren4 QIAO Wei1 GUI Chun1 1 2 3 4

..............page:185-188

Analysis of thermal output of high temperature strain gauge by different measurement methods
LIU Zicai YU Danping LI Xihua LU Yanyan CHEN Xuede LI Pengzhou

..............page:189-192

Study on the thermal fatigue of tee in the first loop of nuclear reactor
HU Lina YU Huajin WANG Yueying

..............page:193-197

Fatigue reliability analysis on the interface of the plane head and the barrel
CHEN Huiliang YAO Weida CAO Ming HUANG Qing XUE Guohong

..............page:198-202

High cycle fatigue analysis of vortex suppression plate and secondary core support structures
XUE Guohong LI Yuan ZHAO Feiyun FENG Shaodong YU Hao

..............page:203-207

Environmentally assistant fatigue analysis for LWR reactor vessel nozzle
SHEN Rui CAO Ming HE Yinbiao TAO Hongxin CHEN Meng

..............page:208-214

Analysis of bearing capacity of CA corner wall in AP1000 nuclear power plant
HUO Changsheng LIU Jianwei LI Shaoping

..............page:270-275

Research on the improvement design for the attachment of supports to AP1000 module wall
LI Cheng LIU Jianwei SHAN Ying

..............page:276-281

Study on the interaction between embedment and concrete in AP1000 nuclear power plant
CHU Yanchun ZUO Shaobing LI Cheng

..............page:282-285

Research of weld residual stress analysis technology of CRDM adapter
JIN Ting XU Xiao XIONG Guangming HUANG Tengfei DENG Xiaoyun

..............page:286-289

Assessment method of secondary loop pipe wall thinning due to flow accelerated corrosion in nuclear power plants
SHI Shaobo1 ZHNANG Wei2 LUAN Xingfeng2 SUN Yu3 1 2 3

..............page:290-294

Optimization design of emergency decay heat removal system for CEFR
TANG Long QI Ming YU Huajin LIU Jia

..............page:295-299

Research on definition of hard rock shear wave velocity of site for nuclear power plant
DING Zhenkun XIA Zufeng

..............page:300-303

Research on working property and early age mechanical property of self-compacting concrete used in steel-concrete structure
ZHAO Yongguang

..............page:304-308

Stress analysis and assessment of RPV core support pads and surround bottom head
GAO Yongjian HE Yinbiao CAO Ming SHEN Rui TAO Hongxin

..............page:309-315

Analysis program for SCV penetration
SONG Yu TIAN Zhenqiang CAI Kun

..............page:316-321

Evaluation of reactor structural function during core drop accident
FENG Shaodong ZHANG Ming ZHU Kun XUE Guohong LI Yuan CHEN Huiliang

..............page:367-371

he ji shu tou gao yao qiu

..............page:375

Finite element analysis of irradiation-induced dilation of the fuel subassembly duct in LMFBR
GAO Fuhai FU Hao LI Nan YANG Kongli WANG Mingzheng

..............page:322-326

Study on the temperature and stress field of steel concrete modular wall
YE Zhiyan LIU Jianwei GE Honghui

..............page:327-332

Fatigue status assessment for reactor pressure vessel based on actual operational transient
ZHU Guangqiang LIAO Changbin DAI Bing GUI Chun

..............page:215-219

Study on the unified constraint parameter for characterizing in-plane and out-of-plane constraint based on the equivalent plastic strain
YANG Jie WANG Guozhen XUAN Fuzhen TU Shandong

..............page:225-231

Failure cases of welds between pressure vessel nozzle and main pipe safe-end in high temperature water environments and relevant research
LI Guangfu

..............page:232-237

OLP embedment design method research for AP1000 nuclear plant
LI Cheng LI Shaoping LIU Jianwei

..............page:333-338

Study of small sample’s high temperature creep behaviors under argon’s protection
XIE Qingyu LU Daogang QIAN Xin HONG Yang DANG Junjie

..............page:238-241

Experimental investigation and ASME code study of creep-fatigue interaction correlation for 316 stainless steel
TAN Xiaohui1 MA Jianzhong1 LIU Yujie2 DAI Zhenyu2 1 2

..............page:220-224