Preface xi
Margin between safety and disaster concerned with nuclear power generation entities
G. C. Sih 1
Basic modelling of creep deformation
Rolf Sandstrom 17
Defect-based structural integrity in nuclear plants
Kamran Nikbin 19
Facilities and research activities for nuclear engineering in radiation research center of Osaka
Prefecture University
Shuichi Okuda et al. 21
Structural integrity issues in nuclear engineering
Shan-Tung Tu 29
Flaw-to-surface proximity rules and fatigue crack growth behavior for transformed surface flaws
Kunio Hasegawa, Yinsheng Li 31
Ductile crack growth simulation of full-scale cracked pipes
Yun-Jae Kim, Jong-Hyun Kim, Nak-Hyun Kim 37
Review and perspective on fracture toughness testing for pressure vessel steels
Xiankui Zhu 39
Finite element analysis on ratcheting strain distribution for pressurized 90o-elbows under cyclic bending
Xiaohui Chen, Xu Chen 51
Some considerations when conducting nuclear power plant structural integrity assessments in the UK
Jinhua Shi 57
Fatigue crack initiation and propagation in stainless steel bars under combined cyclic torsion and tension
Huichen Yu, Yanguo Sun, Keisuke Tanaka 59
In-situ observations on local fracture behavior in a dissimilar metal weld joint of nuclear power plant
Haitao Wang, Guozhen Wang, Fu-Zhen Xuan, Changjun Liu, Shan-Tung Tu 65
Nanoindention on proton irradiated A508-3 steel
Qiangmao Wan, Guogang Shu, Rongshan Wang, Hui Ding, Xiao Peng, Chunxu Pan,
Yang Li, Qi Zhang, Chuansheng Liu 73
Effect of high temperature on integrity of pressure vessels of nuclear power plant in case of severe
unusual accident
Tong Liu, Ke Wang, Qiwu Dong 77
Statistic characteristics of fatigue limit in steels and magnesium alloys
Yoshiharu Mutoh, S. Mohd 83
A numerical fracture mechanics tool to help assess the structural integrity of nuclear power plant
components
Chris Timbrell, Ramesh Chandwani, Angelo Maligno, Charly Ma 91
Finite element analysis and experimental study on drop process of steel containers
Caifu Qian, Hong Xu 97
An energy approach to estimate yield strength by small punch testing
Xiaohui Zou, Kaishu Guan, Tong Xu 101
Damage evaluation for an aged turbine rotor material using creep crack growth tests
Ting Ye, Fu-Zhen Xuan, Zhengdong Wang 107
An energy-based model for prediction of fracture toughness using Charpy size ‘surveillance specimens’
in nuclear power plant
Rui Cheng, Yupeng Cao, Guozhen Wang, Hu Hui, Fu-Zhen Xuan, Zhengdong Wang 113
The exploration of strain aging embrittlement evaluation in metallic materials using indentation test
Jie Tang, Weiqiang Wang, Mengli Li, Haoyuan Kong, Qiang Shi 121
Fracture toughness and impact strength of SUS630 stainless steel
Defu Nie, Yoshiharu Mutoh 127
Creep behavior and microstructural evolution of P92 steel used in ultra supercritical plants
Xiaofeng Guo, Jianming Gong, Yong Jiang 133
Finite element modeling of creep behavior of porous nickel alloys at the operating
conditions of molten carbonate fuel cell
Zhuo He, Jian Chen, Jianjun He, Jianlin Chen, Yanjie Ren, Wei Qiu 139
Prediction of creep rupture property using MHZ constant for 25Cr35Ni steel
Chunhui Liu, Jie Zhao, Congqian Cheng, Lixin Song, Haitao Ma 145
Tensile behavior of a TiAl intermetallic alloy at 750ºC based on in-situ observational tests
Zehui Jiao, Xiping Song, Huichen Yu, Yanguo Sun 149
Prediction methodology of creep performance from stress relaxation measurements
Jinquan Guo, Huichao Shi, Long Tian, Zhanjun Li 157
Corrosion fatigue of tailshaft material in seawater
Shuxin Li, Robert Akid, Shurong Yu 161
The unified model of fatigue crack growth from micro- to macro-scale and its engineering application
Xuesong Tang, Xiaobo Zhang 167
Quantitative inspection of iron contamination on 304 Austenitic stainless steel
Congqian Cheng, Tieshan Cao, Jie Zhao, Guanyu Song 175
Influence of high temperature aging on the carbides of 25Cr35Ni-Nb alloys
Xiaoming Lian, Xuedong Chen, Yunrong Lv, Tao Chen 181
Chemical degradation of elastomeric gasket material in simulated PEM fuel cell environments
Xiaowei Zhang, Jinzhu Tan, Yanchao Xin, Xuejia Hu 187
Limit load analysis of pressure pipe with internal double pits at high temperature
Zhigang Sun, Xiaohua He, Changyu Zhou 193
Characteristics of
ˆ
J -integral and COD values of transverse crack during rolling process
Jianjun Chen, Yuxi Yan, Hongliang Pan 199
LBB analysis of a dissimilar metal weld joint of pipe-nozzle in nuclear power plant
Nu Gong, Guozhen Wang, Fu-Zhen Xuan, Shan-Tung Tu 205
Welding residual stress and crack driving force for centerhole control rod drive mechanism nozzles
in AP1000 RPV head
Zhengjun Gu, Guozhen Wang, Fu-Zhen Xuan, Shan-Tung Tu 213
Fatigue-cracking evolution of material under load action
Jianhua Xiao 221
Research on limit load and defect tolerance for autofrettaged pipes with corrosion
Xing Xin, Jianping Zhao 227
Fatigue life prediction of welded tubular T-joints
Tong Liu, Minshan Liu, Qiwu Dong 233
Influence of environmental conditions on fatigue behavior of a titanium alloy for turbine blade
Yu-Jia Li, Fu-Zhen Xuan, Shan-Tung Tu, Zhengdong Wang 237
Interval sensitivity analysis of fracture failure parameters of titanium pipe with crack
Qiao Dai, Changyu Zhou, Jian Peng, Xiaohua He 243
Notch sensitivity of two materials including TiAl alloys and K418 alloys
R. Cao, H. J. Liu, J. Zhang, J. H. Chen 251
Effect of Sn contamination on fatigue properties of 304 stainless steel
Yan Zhao, Congqian Cheng, Jie Zhao 265
A study on reheat cracking susceptibility of SA543 steel
Huaquan Pu, Xuemei Luo, Wanbo Dou, Xuedong Chen 269
An investigation of intergranular reheat cracking in the weld heat affected zone of TP321H
stainless steel
Tao Chen, Xuedong Chen, Zhibin Ai, Xiaoming Lian 275
Quantitative measurement of strain-induced α´-martensite in 06Cr19Ni10 austenitic stainless steel
Weihai Kong, Xuedong Chen, Pengju Guo, Yongchao Yan 283
Influence of geomagnetic field on the spontaneous magnetic signals of ferromagnetic steel during
tensile testing
Pengju Guo, Weihe Guan, Xuedong Chen 289
The vibration analysis of steam generator support plates coupled with fluids by integral
transformation method
Tong Liu, Qiwu Dong, Minshan Liu 295
Dynamic analysis of supercritical carbon dioxide condenser
Minshan Liu, Jin Xie, Qiwu Dong, Tong Liu 301
Finite element analysis on overall stress variation of the boiler drum of 300MW thermal power unit
during the startup process
Jianjun He, Jian Chen, Guang Li, Wenhui Liu, Wei Qiu, Wei Li 307
Finite element analysis of equivalent fracture stress and strain in small punch specimen
Guangzhe Zhang, Kaishu Guan, Hehui Wang, Xu Wang, Yifei Xu 313
Three-dimensional finite element analysis of temperature field and thermal stress of tube sheet in
U-tube SG model
Minshan Liu, Ruijie Wang, Qiwu Dong, Tong Liu 319
Numerical simulation of the stress distribution of the components in a single PEM fuel cell
Xuejia Hu, Jinzhu Tan, Xiaowei Zhang, Yanchao Xin 325
Nonlinear dynamic response of piezoelectric cylindrical shell with delamination considering
contact effect
Jinhua Yang 331
Pitting of LY12CZ aluminum alloy under corrosion-deformation interactions (CDI)
Sixian Rao, Wei Wei, Xuedong Chen 339
Determination of mechanical properties of laser cladding H13-TiC composite coating
Shengting Gu, Yumei Bao, Guozhong Chai 345
Effect of residual stress on fracture properties of thin films under bending
Xiancheng Zhang, Fu-Zhen Xuan, Zhengdong Wang, Shan-Tung Tu 351
Effect of laser parameters on the mechanical properties of in situ synthesized TiN/Ti3Al composite
coatings on Ti6Al4V
Zhengdao Liu, Jinsha Xu, Xiancheng Zhang, Fu-Zhen Xuan, Zhengdong Wang 361
Effectiveness study of the envelope method for coalescing multiple surface cracks
Xiaoyu Liu, Caifu Qian, Huifang Li, Hui Zheng 367
Mode and frequency selections of ultrasonic Lamb waves for creep damage detection in Titanium alloy
JuanYe, Fu-Zhen Xuan, Yanxun Xiang 371
Nd:YAG laser weldability and tensile strength of AZ91D magnesium alloy butt joints
Chunwei Ma, Peng Sun, Peiquan Xu 377
Cyclic asymmetry of a single-crystal nickel-based superalloy
Ying Li, Huichen Yu, Xueren Wu, Yanguo Sun 385
Author index 389
Keywords in
精彩片段：
Abstract The concern for nuclear power safety was initiated by the International Atomic Energy Agency (IAEA) about 12 years after World War II. Within the commercial arena alone, the safety issues connected with nuclear power generation of electricity are already enormous. They can involve the interactive changes of the combined effects of technical, ecological, economical, social, and political. The heart of the nuclear power plant is the nuclear reactor that can be PWR, BWR, GMR (RBMK) and MSR. Safety operational regulations are presently concerned mostly with the PWR and BWR to which the US NRC coordinates with 14 other countries. As commendable as the tasks performed by the Nuclear Regulatory Commission (NRC) for the past 30 years and more, Codes & Standards (C&S) do age and amendments are necessary. This is especially true for those that require the support of hard core science and advanced technology. Advanced physical laws and computational schemes can enhance the C&S. The revision, validation, and revalidation of the NRC-ASME &III/XI codes, about 10 years ago under the VOCALIST program, however, have not lived up to their intention. The Elastic-Plastic Fracture Mechanics (EPFM) code as part of PVC (Pressure Vessel Code) lost credibility as the elastoplasticity-based J-Integral had no connection with the dislocation theories that were assumed to provide the theoretical mechanics foundation for elastoplasiticy. This hope vanished after the NRC C&S codes were prematurely installed. The possible uses of multiple scaling were by passed, since the 1990s. Certainly, nuclear power safety will not wait for NRC to recognize Multiscale Fracture Mechanics (MFM). Particularly vulnerable are the use of commercial black box programs based on mono-scale parameters such as the J-, C- and C*-Integral for characterizing inherently dual- or multiscale-damage processes that are referred to as Elastic & Plastic (E&P), Creep & Fatigue (C&F), and Stress Corrosion Cracking (SCC). Future code development connected with the Liquid Salt Very High Temperature Reactor (LS-VHTR) cannot afford to disregard the life expectancy of the critical components for each scale range from nano to macro. The J- and C*-Integral are mono-scale by definition. Their replacement by the Generalized Crack Extension Energy (GCEE) G can be accomplished simply by altering the specimen thickness, and loading rate for a given material using Multiscale Fracture Mechanics (MFM). The suggested approach is heuristic since adjustments are needed to remove the ambiguities in applying the J- and C*-Integral. The global (load) energy transferred to the “crack tip” had to be measured correctly. This required a knowledge that the singularity point (absorbing-dissipating energy in tandem) can be assumed to characterize the phantom crack tip as inhaling and exhaling in breathing at the different spatial-temporal scales. Keep in mind that not all of the input energy is absorbed. Some can be dissipated. This mass pulsation behavior is described in the theory of “Crack Tip Mechanics” (CTM). The pulsation energy model was necessary for determination of the multiscale crack tip location. A consistent interpretation of the fracture mechanics test data was thus made possible.
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