Proceedings of the
ASME Pressure Vessels
and Piping Conference
- 2010 -
VOLUME 1
Codes and Standards
presented at
ASME 2010 PRESSURE VESSELS AND PIPING DIVISION/K-PVP CONFERENCE
JULY 18-22, 2010
BELLEVUE, WASHINGTON, USA
sponsored by
PRESSURE VESSELS AND PIPING DIVISION, ASM!
ASM E
Three Park Avenue New York, N.Y. 1 00 1 6>
CONTENTS
CODES AND STANDARDS
API 579/ASME CODE FITNESS-FOR-SERVICE ACTIVITIES
Introduction 1
PVP2010-25500 3
Discussion on Plastic Collapse Criterion at High Temperatures in FFS Assessment Rules
Kenji Oyamada, Shinji Konosu, Hikaru Miyata, and Takashi Ohno
PVP2010-25508 15
Development of Fragility Curve Considering Aging of Oil Storage Tanks and its ApplicationTo Risk Assessment of Industrial Complexes
Yoshihisa Murakami, Toshiro Yamase, Shinsaku Zama, Yoshihiro Hirokawa,Haruki Nishi, Minoru Yamada, Akiko Hirano, and Naoya Kasai
PVP2010-25537 19
Research and Development of a Double Steel Bottom Structure of Oil Storage Tank
Zhiping Chen, Liuchuan Yan, Zhou Fang, and Guowei Cao
PVP2010-25810 27
Comparison of Thermo-Mechanical Fatigue Life Assessment Methods for Coke Drums
Jorge A. Penso and Radwan Hazime
ASME CODE SECTION XI ACTIVITIES
Introduction 37
PVP2010-25145 39
Technical Basis for a Flaw Tolerance Option for Code Case N-770-1 for Large Diameter
Cold Leg Piping to Main Coolant Pump Welds With Obstructions
Warren Bamford, Reddy Ganta, Gordon Hall, and Matthew Kelley
PVP2010-25728 51
Universal Weight Function Consistent Method to Fit Polynomial Stress Distribution for
Calculation of Stress Intensity Factor
Douglas A. Scarth and Steven X. Xu
PVP2010-25741 67
Alternate Flaw Acceptance Criteria for Flaws in Ferritic Steel Vessels Operating in the
Upper Shelf RangeH. L. Gustin, R. C. Cipolla, and D. A. Scarth
PVP2010-26164 73
Technical Basis for Case N-766 Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigationof PWR Full Penetration Circumferential Nickel Alloy Welds in Class 1 Items
Paul Donavin, S. Marlette, W. Bamford, K. Stuckey, and G. Poling
ix
COMBINATION OF MULTI-AXIAL LOADS IN DESIGN AND
FITNESS-FOR-SERVICE RULES
Introduction 79
PVP2010-25101 81
Prediction Method for Plastic Collapse of Pipes Subjected to Combined Bending and
Torsion Moments
Yinsheng Li, Kunio Hasegawa, Phuong H. Hoang, and Bostjan Bezensek
PVP2010-25102.. 89
Effect of Pressure on Plastic Collapse Under the Combined Bending and Torsion Moments
for Circumferentialiy Surface Flawed Pipes
Yinsheng Li, Wataru Ida, Kunio Hasegawa, Bostjan Bezensek, and Phuong H. Hoang
PVP2010-25133 99
Proposal for Inclusion of Torsion in Section XI Flaw Evaluation Procedures for Pipes
Containing Surface Crack-Like Flaws
Bostjan Bezensek, Yinsheng Li, Kunio Hasegawa, and Phuong H. Hoang
PVP2010-25283 107
Effects of Torsion on Equivalent Bending Moment for Limit Load and EPFM Circumferential
Pipe Flaw Evaluations
Phuong H. Hoang, Kunio Hasegawa, Bostjan Bezensek, and Yinsheng Li
ELASTIC-PLASTIC ANALYSIS AND FATIGUE ISSUES IN
PRESSURE VESSEL DESIGN
Introduction 123
PVP2010-25097 125
A Hierarchical Finite Element Framework for the Assessment of Pressure Vessels to the
ASME III Code
Michael Martin, Lindsay Rawson, and David Rice
PVP2010-25320 137
Analysis of ASME Codes for Fatigue of Pressure Vessels
Khalil Farhangdoost and Peyman Hamrahan
PVP2010-25648 145
Expressions of Load and Structural Deformation Relationship for Cylindrical and SphericalVessels Under Internal Pressure
Yang-chun Deng and Gang Chen
EMERGING CODES AND STANDARDS
Introduction, 153
PVP2010-25308 155
Recent Progress of the Stationary Pressure Vessel Regulations and Standards in China
Binan Shou, Gang Chen, and Tiejun Xie
x
PVP2010-25530 161
Recent Activity of KEPIC Application for Construction and Operation of Nuclear Power
Plants in Korea
Hoonseok Byun, Jonghae Kim, Youngho Son, and Banuk Park
PVP2010-25906 167
Classification Method in Chinese Supervision Regulation on Safety Technology for
Stationary Pressure Vessel
Linlin Wu, Binan Shou, Tiejun Xie, Zhaohui Chen, and Ping Xu
PVP2010-25923 175
Using Industry Standards for Designing Composite Repair Systems for Corroded
Process PipingChris Alexander and Franz Worth
PVP2010-25945 v. 185
Flexibility Factors for High Density Polyethylene Elbows
Rudolph J. Scavuzzo, Charles N. Papadelis, and Siegrid Hall
PVP2010-26069 197
High-Energy Piping Systems are Now Covered Piping Systems
Joseph Frey
ENVIRONMENTAL FATIGUE ISSUES
Introduction 201
PVP2010-25181 203A Study on the Temperature Calibration for a Small Electrical Resistance Furnace
Un-Bong Baek, Hae Moo Lee, Yun-Hee Lee, and Seung Hoon Nahm
PVP2010-25194 209Effects of Continuous Strain Rate Changing on Environmental Fatigue for Stainless SteelsIn PWR Environment
Yuichiro Nomura, Seiji Asada, Takao Nakamura, and Masakazu Tanaka
PVP2010-25564,
215Thermal Aging Effect on Environmental Fatigue Life of CF8M Cast Stainless Steel at
Strain Rate 0.04%/s Under PWR Operating Condition
lll-Seok Jeong, Wan-Jae Kim, and Hyun-lk Jeon
PVP2010-25677 221Status Report on ASME Section III Subgroup on Design Plan for Code Changes to
Implement Environmental Fatigue Evaluation Methods
Jack R. Cole and John C. Minichiello
PVP2010-25947 227Strain Rate Calculation Approach in Environmental Fatigue Evaluations
Mark A. Gray, Matthew C. Salac, David H. Roarty, and E. Lyles Cranford III
xi
PVP2010-26027 233
Effect of Loading Signal Shape and of Surface Finish on the Low Cycle Fatigue Behavior
of 304L Stainless Steel in PWR Environment
Jean Alain Le Duff, Andre Lefrangois, Jean Philippe Vernot, and Delphine Bossu
FUSION REACTOR COMPONENT RULES FOR STRUCTURAL INTEGRITY
Introduction 243
PVP2010-25128 245
ASME Division IV Magnetic Confinement Fusion Energy Devices
William Sowder and Richard W. Barnes
PVP2010-26008 249
Evaluation of Strength on Dissimilar Metal Joints for ITER First Wall ComponentsH. Nishi, M. Enoeda, T. Hirose, D. Tsuru, and H. Tanigawa
PVP2010-26116 257
Current Fusion Standards and Other Related Activities in Japan
Yuji Nakasone, Kazuyoshi Sato, and Yukio Takahashi
PVP2010-26123 263
Manufacturing Technologies of Breeding Blanket Components Using Reduced Activation
Ferritic/Martensitic Steel
Takanori Hirose, Hiroyasu Tanigawa, and Mikio Enoeda
HARMONIZATION FOR MATERIAL DATA AMONG
FITNESS FOR-SERVICE CODES
Introduction 267
PVP2010-25119 269
Outline of the JSME Mandatory Rules for Thermal Power Generation Facilities as the
Harmonized Code in the Regulatory RequirementsKazuhiro Kimura, Seiichi Hamada, and Masaaki Fujita
PVP2010-25187 275
Toward International Harmonization of Nuclear Codes and Standards
Claude Faidy
PVP2010-25247 283
Assessment of Fatigue Crack Growths for Transformed Surface Flaws Using FFS Codes
Kunio Hasegawa and Yinsheng Li
PVP2010-25939 289
Comparison of Fatigue Crack Growth Curves of Japan, the US and EU Code and Standards
Kiminobu Hojo and Yukio Takahashi
xii
HIGH TEMPERATURE CODES AND STANDARDS
Introduction 295
PVP2010-25258 297
Applications of Code Case 2605 for Fatigue Evaluation of Vessels Made in 2.25Cr-1 MO-0.25V
Steels Slightly Into Creep RangeSusumu Terada
PVP2010-25354 307
Evaluation of Creep-Fatigue Damage for Prototype Process Heat Exchanger of the
NHDD Plant
Hyeong-Yeon Lee, Kee-Nam Song, Yong-Wan Kim, Sung-Deok Hong, and
Hong-Yune Park
PVP2010-25414 315
Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels
Naoto Kasahara, Kenichiro Satoh, Kazuyuki Tsukimori, and Nobuchika Kawasaki
PVP2010-25489 323
Verification of the Prediction Methods of Strain Range in Notched Specimens Made of
Mod.9Cr-1Mo
Masanori Ando, Yuichi Hirose, Shingo Date, Sota Watanabe, Yasuhiro Enuma, and
Nobuchika Kawasaki
PVP2010-25556 335
Stress and Strain Locus of Perforated Plate in Inelastic Deformation: Strain-Controlled
Loading Case
Osamu Watanabe, Bopit Bubphachot, and Akihiro Matsuda
INTERACTION AND MODELING FOR MULTIPLE FLAWS
Introduction 345
PVP2010-25134 347
An Engineering Approach to Characterisation of Twin Flaws in CleavageBostjan Bezensek, John Sharpies, and Mark Wilkes
PVP2010-25199 355
Behavior of Plastic Collapse Moments for Pipes With Two Non-Aligned Flaws
Kunio Hasegawa, Katumasa Miyazaki, and Koichi Saito
PVP2010-25317 363
Growth Behavior of Two Interacting Surface Cracks of Dissimilar Size (Comparison for
Tensile and Bending Load)
Masayuki Kamaya, Masanori Kikuchi, and Eiichi Miyokawa
PVP2010-25453 371
Simulation of Ductile Fracture of Multiple Flaws
Masanori Kikuchi, Kazuhiro Suga, and Shota Kawasaki
xiii
PVP2010-25497 379
Fracture Assessment of Austenitic Stainless Steel Piping With Multiple Flaws in
Heat-Affected Zone
Chihiro Narazaki, Toshiyuki Saito, Masao Itatani, Takuya Ogawa, and Takao Sasayama
PVP2010-25992 383
Coalescence of Complex Cracks in Ex-Service Carbon Steel Pipe Bends DuringBurst Pressure Tests
Xinjian Duan, Michael J. Kozluk, Tracy Gendron, and John Slade
MULTI-AXIAL FATIGUE BEHAVIOR OF VESSEL AND PIPING MATERIALS
FOR DESIGN AND EVALUATION RULES
Introduction .399
PVP2010-25154 401
Crack Growth Analysis in Weld-Heat Affected Zone Using S-Version FEM
Masanori Kikuchi, Yoshitaka Wada, Yuto Shimizu, and Yulong Li
PVP2010-25197 407
Effect of Km on Fatigue Crack Growth Behavior
Masanori Kikuchi, Yoshitaka Wada, and Chikako Ohdama
PVP2010-25241 415
Closure Effect on Interaction of Two Surface Cracks Under Cyclic Bending
Masanori Kikuchi, Yoshitaka Wada, Maigefeireti Maitireyimu, and Hirotaka Sano
PVP2010-25472 423
Fatigue Behavior of Circumferentially Notched Round Bars of Austenitic Stainless Steel
Under Torsional and Axial Loads
Masao Itatani, Keisuke Tanaka, Isao Ohkawa, Takehisa Yamada, and Toshiyuki Saito
PVP2010-25527 433
On Mixed Mode Crack Propagation Analysis Based on VCCM
(Virtual Crack Closure-Integral Method) for Tetrahedral Finite Element
Hiroshi Okada, Hiroshi Kawai, Takashi Tokuda, and Fukui Yasuyoshi
PVP2010-25831 443
Experimental Investigations of Fatigue Crack Propagation for Pipe Under Torsional LoadingMotoki Nakane, Satoshi Kanno, Shota Hashimoto, Takayuki Watanabe, and
Yukio Takahashi
PVP2010-25950 451
Numerical 3-D Fatigue Crack Growth Analyses of Real-Life ComponentsDaniel Bremberg and Guido Dhondt
PVP2010-25972 459
A Study on Behavior of Mixed Mode Fatigue Crack Growth of Spiral Welding Part Under
Bending Load
Jung-Hun Choi, II Hwan Kim, Jae-Mean Koo, and Chang-Sung Seok
xiv
PVP2010-25996 465
Low Cycle Fatigue Life of Type 316 Stainless Steel Notched Specimen Under Proportionaland Non-Proportional Multiaxial Loadings
Takamoto Itoh
PVP2010-26015 473
Multiaxial Fatigue Failure Criterion Considering Formation and Growth of Small Cracks
Yukio Takahashi
PROBABILISTIC AND RISK BASE ASSESSMENT FOR
CODES AND STANDARDS
Introduction 481
PVP2010-25240 483
Effects of Several Factors on the Solution of Failure Probability of Pipes in Nuclear
Power Plants
Jai Hak Park, Jae Bong Lee, and Young Hwan Choi
PVP2010-25395 491
Incorporation of Materials' Sensitive Simulation Technique Into the PINTIN-CAM Code for
Integrity of Nuclear Piping SystemDebashis Datta and Changheui Jang
PVP2010-25665 499
Analysis Method of Failure Likelihood on Pressure Equipment With Combined Action of
Multi-Failure Mechanism
Xuedong Chen, Zhibin Ai, Tiecheng Yang, Jiushao Hu, and Chuanqing Cheng
PVP2010-25917 505
Failure Probability Analysis by Probabilistic Fracture Mechanics Based on FRI SCC Model
Noriyoshi Maeda and Tetsuo Shoji
PVP2010-25993 513
Partial Safety Factors Assessment of Pipes With a Circumferential Surface Flaw
Hideo Machida, Manabu Arakawa, and Hiromasa Chitose
PVP2010-26028 521
Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress
Analysis and Probabilistic Fracture Mechanics
Makoto Udagawa, Jinya Katsuyama, and Kunio Onizawa
RATCHETING ISSUES IN PRESSURE VESSEL DESIGN
Introduction 531
PVP2010-25415 533
Ratcheting Assessment of a Fixed Tube Sheet Heat Exchanger Subject to in Phase Pressure
and Temperature CyclesKhosrow Behseta, Robert Hamilton, and Donald Mackenzie
xv
PVP2010-25753 541
Review and Assessment of Ratcheting Considerations for Design and Analysis
Yogendra S. Garud
PVP2010-25761 545
Effect of Ovality on Shakedown of Pipe Bends
Ali Asadkarami, Wolf Reinhardt, and Nima Zobeiry
PVP2010-25911 555
Non-Cyclic Shakedown-Ratcheting Boundary Determination: Analytical Examplesft Adibi-Asl and W. Reinhardt
PVP2010-26088 565
Lower Bound Methods in Elastic-Plastic Shakedown AnalysisWolf Reinhardt and Reza Adibi-Asl
REACTOR VESSELS AND REACTOR CORE INTERNALS FOR
CODES AND STANDARDS
Introduction 575
PVP2010-25525 577
Overview of Code Case on Alternative Design Methodology by Using Elastic-Plastic
Finite Element Analysis for Class 1 Vessels in the JSME Rules on Design and Construction
Seiji Asada, Takashi Hirano, Tetsuya Nagata, and Naoto Kasahara
PVP2010-25561 585
Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor
Pressure Vessel Steels
Jinya Katsuyama, Tohru Tobita, Yutaka Nishiyama, and Kunio Onizawa
PVP2010-25862 593
Evaluation of Fracture Toughness by Master Curve Approach Using Miniature
C(T) SpecimensNaoki Miura and Naoki Soneda
PVP2010-25974 603
Thermal Aging and Neutron Embrittlement Evaluation of Cast Austenitic Stainless Steels
Hardayal S. Mehta, Brian D. Frew, Ronald M. Horn, Fred Hua, Sampath Ranganath, and
Robert G. Carter
RECENT DEVELOPMENTS IN ASME CODES AND STANDARDS
Introduction.
615
PVP2010-25107 617
Review of Section VIII, Division 1 and 2 Changes, 2008-2010
Thomas P. Pastor
xvi
PVP2010-25349 62B
Development of ASME Section X Code Rules for High Pressure Composite HydrogenPressure Vessels With Non-Load Sharing Liners
Norman L Newhouse, George B. Rawls, Mahendra D. Rana, Bernard F. Shelley, and
Michael R. Gorman
PVP2010-25451 635
Technical Basis of Material Toughness Requirements in the ASME B&PV Code,
Section VIII, Division 2
David A. Osage and Martin Prager
PVP2010-25471 ...653
Flaw Testing of Fiber Reinforced Composite Pressure Vessels
John Makinson and Norman L. Newhouse
PVP2010-25720 .....U 661
An Approach Based on Code Case 2605 for Fatigue Evaluation of Vanadium Modified
Materials Reactor
M. Sohel M. Panwala, D. H. Desai, and S. L. Mehta
RECENT DEVELOPMENT IN CHINESE CODES AND STANDARDS
Introduction 667
PVP2010-25189 669
Time-Dependent Risk Control of Crucial Tube Furnace With SIL Requirement Considered
Jianxin Zhu, Xuedong Chen, Zhibin Ai, and Weihe Guan
PVP2010-25285 675
RBI Technology for Boiler Superheater of Power Station
Fujun Liu, Shoubao Ding, Shuai Kong, Dan Song, Dongming Hu, Xiaolian Guo, and
Nanhui Jin
PVP2010-25306 683
The Typical Steels of Equipment in China
Shangzhi Zuo, Binan Shou, and Guoyi Yang
PVP2010-25316 689
Conception and Current Progress of China In-Service Pressure Equipment Inspection and
Assessment Regulation and Standard SystemGuodong Jia, Binan Shou, Hut Wang, Jin Shi, Guoshan Xie, Haiyi Jiang, Yanze Chen,
and Zhaohe Chen
PVP2010-25398 697
Guidance of Equipment Risk Management With RBI TechniquesYu Qu, Xiangmin Hao, Anhe Jiang, and Mingchao Gao
PVP2010-25400 703
Guaranteeing Long-Cycle Safe Operation of Ethylene Plants by RBI TechnologyZhibin Ai, Xuedong Chen, Tiecheng Yang, Jiushao Hu, and Chuanqing Cheng
xvii
PVP2010-25425 709
Numerical Design of Tubesheet Structure Based on Finite Element Analysis
Xiaodong Yu, Caifu Qian, and Hongjie Yu
PVP2010-25576 713
Classification of Defects in Fusion Joints of Polyethylene Pipes
Jinyang Zheng, Yongquan Qin, Jianfeng Shi, Weican Guo, Hui Wang, and Fei Wang
PVP2010-25578 721
Development of Non-Destructive Test and Safety Assessment of Electrofusion Joints for
Connecting Polyethylene Pipes
Jinyang Zheng, Jianfeng Shi, and Weican Guo
PVP2010-25581 731
Experimental Investigation on Coupling Focusing Ultrasonic Technique for Inspection of
Polyethylene Butt-Fusion Joint
Weican Guo, Jinyang Zheng, Zhongqiang Liu, Jianfeng Shi, Shoubao Ding, and
Shangzhi Zuo
PVP2010-25905 737
Effect of Strain Rate on the Deformation-Induced Martensite Transformation and
Mechanical Behavior of Austenitic Stainless Steels for Cold Stretched Pressure Vessels
Cunjian Miao, Yaxian Li, and Jinyang Zheng
PVP2010-25932 743
A Method for Detecting the Cold Welding and Optimizing the Welding Procedure for the
Electro-Fusion Joints in PE Pipes
Ping Xu, Weican Guo, Shoubao Ding, Shangzhi Zuo, and Ping Shi
PVP2010-26064 751
Seismic Behavior of Buried PE Pipelines Subject to Fault Offsets
Michael J. O'Rourke, Tarek H. Abdoun, and Da Ha
RECENT DEVELOPMENTS IN EUROPEAN CODES AND STANDARDS
Introduction 769
PVP2010-25085 771
Flaw Evaluation in Elbows Through French RSEM Code
Claude Faidy
PVP2010-25582 779
The Future of the BS 7910 Flaw Assessment Procedures
Isabel Hadley, Bob A. Ainsworth, Peter Budden, and John Sharpies
PVP2010-25624 791
Verlife - Unified Procedure for Lifetime Assessment of Components and Piping in
WWER NPPs During Operation: Updating and Further DevelopmentMilan Brumovsky
xviii
PVP2010-25673 797
Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors
(RR) and Fusion (ITER): General Overview
T. Lebarbe, S. Marie, B. Drubay, O. Gelineau, D. Bonne, and Frantz De La Burgade
PVP2010-25679 803
Codification of 316LN in RCC-MR Code: Experience and Prospective Projects
D. Bonne, S. Dubiez-Le Goff, and B. Drubay
PVP2010-25683 809
Evolution in the Italian Standard for Creep-Operated Pressure EquipmentOttaviano Grisolia and Corrado Delle Site
PVP2010-26030 821
RCC-M: Content, Working Approach, and Future Evolutions
Jean-Marie Grandemange and Philippe Malouines
RECENT DEVELOPMENTS IN JAPANESE CODES AND STANDARDS
Introduction 837
PVP2010-25153 839
Effect of Overload on the Threshold Stress Intensity Factor Range of SUS316 as a
Function of Crack Size
Kotoji Ando, Koji Takahashi, Yasuaki Hashikura, and Keiji Houjyou
PVP2010-25155 845
Effect of Shot Peening on Fatigue Limit of Surface Flawed SampleKotoji Ando, Fumio Takahashi, Akira Tange, and Yoshiki Ono
PVP2010-25203 851
Failure Probability of Degraded Pipes Based on Probabilistic Fracture Mechanics for
Seismic Safety Margin Assessment on NPP
Yinsheng Li, Masaki Nakagawa, Katsumi Ebisawa, Shinobu Yoshimura, and
Hiroyuki Kameda
PVP2010-25205 861
Seismic Safety Margin Assessment for Electrical Components Utilizing Full-Scale Test
Toru lijima, Masaki Nakagawa, Akira Shibuya, Katsumi Ebisawa, and Hiroyuki Kameda
PVP2010-25206 869
Seismic Safety Margin Assessment for Thin-Wall Cylindrical Tanks UtilizingUltimate Strength Test
Toru lijima, Masaki Nakagawa, Akira Shibuya, Katsumi Ebisawa, and Hiroyuki Kameda
PVP2010-25253 879
Seismic Safety Margin Assessment for NPP Utilizing Full-Scale Tests: Overview
Hiroyuki Kameda, Masaki Nakagawa, Akira Shibuya, Shiro Fukunishi, and
Katsumi Ebisawa
xix
PVP2010-25321 88S
Finite Element Analyses of Residual Stresses in Typical Welded Joints Used in Nuclear
Power Plants and Comparisons With ExperimentsDean Deng, Kazuo Ogawa, Nobuyoshi Yanagida, and Koichi Saito
PVP2010-25495 897
Damage Observations of the Straight Pipes Subjected to Cyclic Load Amplitudes of
Various Levels
Izumi Nakamura, Akihito Otani, and Masaki Shiratori
PVP2010-25610 905
Improvement of the Threshold Stress Intensity Factor for Stress Corrosion Cracking in
SUS316 by Tensile Overload
Koji Takahashi, Yuji Miyazaki, Yasuaki Hashikura, and Kotoji Ando
PVP2010-25645 911
Fracture Assessment for Butt Welded Plate of Ni-Based AlloyMasao Itatani, Takuya Ogawa, Toshiyuki Saito, Chihiro Narazaki, and Kazuo Ogawa
PVP2010-25818 917
Crack Branching and its Effect on Environmentally Assisted Cracking in High TemperatureWater Environments
Zhanpeng Lu, He Xue, and Tetsuo Shoji
PVP2010-25936 929
Sensitivity Analysis of Residual Stress Simulation of Dissimilar Metal Joint of Safe End
Nozzle and Key Issues for Standard Procedure to Maintenance Rules
Kiminobu Hojo, Kazuo Ogawa, Naoki Ogawa, and Haw Muroya
PVP2010-26114 941
Fracture Evaluation Using Limit Analysis for Complex Structure (Pressure Load)Kiminobu Hojo, Mayumi Ochi, Kazuo Ogawa, and Naoki Ogawa
PVP2010-26120 953
Ductile Fracture Strength of Ni-Based Alloy With an Inch Thickness
Katsumasa Miyazaki and Koichi Saito
PVP2010-26121 959
Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth
Rate in Boiling Water Reactor Operational Condition: Part 2—The Effect of SingleOverload on SCC Growth Behavior
Yuzuru Ito, Masahiro Saito, Qunjia Peng, Jiro Kuniya, and Tetsuo Shoji
PVP2010-26135 969
Influencing Factors for Improving Accuracy in Prediction of Stress Corrosion Crack Growth
Rate in Boiling Water Reactor Operational Condition: Part 1 —Prediction of SCC Growth Rate
in Terms of Vickers Hardness
Yoichi Takeda, Zhanpeng Lu, Takeshi Adachi, Qunjia Peng, Jiro Kuniya, and Tetsuo Shoji
xx
PVP2010-26136 977
Contributory Factors to Accurate Prediction of Rate of Stress Corrosion Cracking in BoilingWater Reactor Under Unexpected Condition During Operation: Part 3—The Effect of HighLoading Rate on SCC Growth Behaviour
Yuji Tanabe, Takeo Tamura, Kenji Suzuki, Jiro Kuniya, and Tetsuo Shoji
RECENT DEVELOPMENTS IN KOREAN CODES AND STANDARDS
Introduction 985
PVP2010-25612 987
Low Cycle Fatigue Behavior and Seismic Asessment for Elbow Pipe Having Local
Wall ThinningYoshio Urabe, Koji Takahashi, and Kotoji Ando
PVP2010-25937 993
An Investigation on Stress Concentration of Local Wall Thinning in Feeder Elbow PipeJong Sung Kim and Jae Seok Seo
PVP2010-25999 999
Diagnostics of Nuclear Power Plant Components Due to Thickness Measurement by UsingDigital Radiography
Masahito Mochizuki, Satoshi Kanno, Shunichi Shimizu, and Yuichi Daitou
REPAIR, REPLACEMENT AND MITIGATION FOR
FITNESS-FOR-SERVICE ACTIVITIES
Introduction 1007
PVP2010-25007 1009
Changes in Section XI: Repairs and Replacements (2007 Through 2009)Ronald A. Yonekawa and Edward B. Gerlach
PVP2010-25931 1015
Development of Stress Reduction Method in the Pipe Welded Zone by HeatingYuka Fukuda and Shinobu Okido
PVP2010-26117 1023Current Status of RRA Rules Development in JSME Fitness-for-Service Code
Koji Dozaki, Satoshi Yamamoto, and Koji Koyama
PVP2010-26134 1031Ambient Temperature Temperbead Welding Using the Underwater Laser Beam
Welding Process
Bruce Newton
xxi
STRUCTURAL INTEGRITY OF PRESSURE COMPONENTS
Introduction 1037
PVP2010-25009 1039
ASME B31.3 End of Life Considerations: Corrosion, Mechanical Strength, and
Small Bore GeometryDennis K. Williams
PVP2010-25184 1045
Finite Element Analysis of Residual Stresses in Butt Welding of Stainless Steel Plates
by GTAW
Gurinder Singh Brar and Rakesh Kumar
PVP2010-25309 1049
Safety Classification Informed Structural Integrity Assessment of Nuclear Plant
ComponentsC. D. Bell, C. T. Watson, J. Howson, and A, E. Walker
PVP2010-25697 1059
The Role of Research in Standards DevelopmentDan Andrei
Author Index 1063
xxii