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