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  • Proceedings of the

    ASME Pressure Vessels

    and Piping Conference

    -2011 -

    VOLUME 1

    Codes and Standards

    presented at

    ASME 2011 PRESSURE VESSELS AND PIPING CONFERENCE

    JULY 17-21, 201 1

    BALTIMORE, MARYLAND, USA

    sponsored byPRESSURE VESSELS AND PIPING DIVISION, ASMf

    ASME

    Three Park Avenue* New York, N.Y. 10016

  • CONTENTS

    CODES AND STANDARDS

    API 579/ASME CODE FITNESS-FOR-SERVICE ACTIVITIESIntroduction 1

    PVP2011-57145 3Effect of Local Geometric Imperfections on Axial Buckling of Welded Steel Tanks

    Zhiping Chen, Chulin Yu, Shunjuan Yan, Licai Yang, and Guowei Cao

    PVP2011-57897 11

    Emergency Relief of Internal Pressures From Aboveground Storage TanksMark Baker and George L. Morovich

    ASME/NRC SYMPOSIUM ON NUCLEAR CODES AND STANDARDSIntroduction 17

    PVP2011-57208 19Evaluation of the Minimum Temperature Requirements for the RPV Closure Head FlangeRegion in 10 CFR 50 Appendix G

    Eric M. Focht

    PVP2011-57321 27Failure Probability Assessment of Piping Systems Affected by SCC and Pipe Wall Thinningfor LBB Analysis

    Hiromasa Chitose, Hideo Machida, and Itaru Saito

    PVP2011-57531 35

    Extremely Low Probability of Rupture (xLPR) Version 1.0 Code: Pilot Study Problem ResultsD. Rudland and C. Harrington

    PVP2011-57680 47Use of LBB Methodology to Support the Transition Break Size ConceptJames E. Nestell and David W. Rackiewicz

    PVP2011-57742 57An Investigation of the Adequacy of a Simplified Boundary Integral Equation/InfluenceFunction Equation Linear Elastic Fracture Mechanics Solution for Nozzle Corner Cracking

    Daniel Sommerville, Minghao Qin, and Eric Houston

    PVP2011-57829 69

    Changing the Frequency of Inspections for PWSCC Susceptible Welds atCold Leg Temperatures

    Nathan A. Palm, Warren H. Bamford, and Craig Harrington

    ix

  • PVP2011-57911 85

    Technical Basis for Proposed Weight Function Method for Calculation of Stress IntensityFactor for Surface Flaws in ASME Section XI Appendix A

    Steven X. Xu, Douglas A. Scarth, and Russell C. Cipolla

    PVP2011-57932 101

    Prediction of Fracture Toughness Transition From Tensile Test Data ApplyingNeural Networks

    Ivo Dlouhy, Hynek Hadraba, Zdenek Chlup, Libor Valka, and LiborZak

    PVP2011-57939 107

    Robust LBB Analyses for Atucha II Nuclear Plant

    G. Wilkowski, B. Brust, T. Zhang, G. Hattery, S. Kalyanam, D. J. Shim, E. Kurth, Y. Hioe,

    M. Uddin, J. J. Johnson, O. R. Maslenikov, A. Gurpinar, A. P. Asfura, B. Sumodobila,A. A. Betervide, and O. Mazzantini

    PVP2011-57941 121

    Lessons Learned for Nuclear Piping Integrity in New ReactorsG. Wilkowski, F. Brust, P. Krishnaswamy, K. Wichman, and D.-J. Shim

    PVP2011-57954 133

    PWSCC Crack Growth Mitigation With InlayDavid Rudland, Frederick W. Brust, D. J. Shim, and G. Wilkowski

    PVP2011-57974 139

    PWSCC Crack Growth Modeling ApproachesF. W. Brust, D.-J. Shim, G. Wilkowski, and D. Rudland

    PVP2011-57978 147

    Leak-Before-Break Assessment in JSME StandardYukio Takahashi

    PVP2011-57982 153

    Effects of Weld Overlays on Leak-Before-Break MarginsG. Angah Miessi, Peter C. Riccardella, and Peihua Jing

    PVP2011-58018 159

    Plastic Collapse Moment for Weld Overlay Pipe With Multiple Circumferential FlawsKunio Hasegawa, Yinsheng Li, and Masayoshi Shimomoto

    PVP2011-58035 167

    A Study of the Key Parameters Affecting the Design of Optimized Weld OverlaysDoug Killian, SamerMahmoud, Heqin Xu, Silvester Noronha, and Ashok Nana

    PVP2011-58041 177

    Implementation of ASME Code, Section XI, Code Case N-770, on Alternative ExaminationRequirements for Class 1 Butt Welds Fabricated With Alloy 82/182Edmund J. Sullivan and Michael T. Anderson

    x

  • COMBINATION OF MULTI-AXIAL LOADS IN DESIGN AND

    FITNESS-FOR-SERVICE

    Introduction 183

    PVP2011-57144 185

    Study on Stress Intensity Factors of Fatigue Crack in Round Bar Under Rotary Bending

    Maigefeireti Maitireyimu, Masanori Kikuchi, and Hiroko Kitano

    PVP2011-57455 191

    Experimental Investigation on the Failure Estimation Method of Cracked CylindersSubjected to Multi-Axial Loads

    Yinsheng Li, Kunio Hasegawa, Naoki Miura, and Katsuaki Hoshino

    PVP2011-57731 199

    Effects of Bending Moment and Torsion on the Internal Pressure Limit Load of

    Locally Thinned PipesPhuong H. Hoang, Kunio Hasegawa, Bostjan Bezensek, and Yinsheng Li

    PVP2011-57839 215

    Evaluation of Torsion and Bending Collapse Moments for Pipes With Local Wall ThinningKunio Hasegawa, Yinsheng Li, Bostjan Bezensek, and Phuong Hoang

    PVP2011-57856 223

    Inclusion of Torsion With Bending and Pressure Loads for Pipes With Thin-Wall RegionsBostjan Bezensek, Yinsheng Li, Kunio Hasegawa, and Phuong Hoang

    ENVIRONMENTAL FATIGUE ISSUES

    Introduction 229

    PVP2011-57083 231

    A Consideration of Margin on Fatigue Design Curves for Carbon and Low-Alloy SteelsMakoto Higuchi, Masahiro Takanashi, Ichiro Tamura, and Toshiaki Takada

    PVP2011-57094 237

    Survey of Ke-Factor on Strain for Strain Rate in Environmental Fatigue Evaluation

    Seiji Asada

    PVP2011-57274 243

    Use of NUREG/CR-6909 Environmentally-Assisted Fatigue Rules for a Nuclear Plant LicenseRenewal Application

    William F. Weitze, Matthew C. Walter, and Keith R. Evon

    PVP2011-57435 247

    Examination of Factors in the Modified Rate Approach Method Under Various ConditionsYuichi Fukuta, Seiji Asada, Yuichiro Nomura, and Hiroshi Kanasaki

    PVP2011-57651,

    257

    Investigation of Differences in the Finite Element Solution of a Sample Fatigue Cumulative

    Usage Factor Calculation Problem

    Gary L. Stevens, Howard J. Rathbun, and Timothy D. Gilman

    xi

  • PVP2011-57943 267

    Discussion on Fatigue Design Curves for Stainless Steels

    Jussi Solin, Sven Reese, and Wolfgang Mayinger

    FUSION REACTOR COMPONENT RULES FOR STRUCTURAL INTEGRITY

    Introduction 273

    PVP2011-57143 275

    Fabrication Design and Code Requirements for the ITER Vacuum VesselH. J. Ahn, B. C. Kim, J. W. Sa, Y. J. Lee, K. H. Hong, H. S. Kim, J. S. Bak, K. J. Jung,

    K, H. Park, T. S. Kim, J. S. Lee, Y. K. Kim, H. J. Sung, K. loki, B. Giraud, C. H. Choi, andY, Utin

    PVP2011-57284 285

    Validation of Fabricability for ITER TF Coil Structures

    Yutaka Chida, Masahide Iguchi, Hideo Nakajima, Koichi Oosemochi, Kenichiro Niimi,and Daisuke Tokai

    PVP2011-57440 291

    Manufacturing Status of JT-60SA Vacuum Vessel and the Related Technology of WeldingYusuke K. Shibama, Kei Masaki, Shinji Sakurai, Kiyoshi Shibanuma, and Akira Sakasai

    PVP2011-57609 301

    Application of ASME Codes for ITER ComponentsAnne Chaudouet, Gilles Bourgeois, and Stephan Carbonneau

    PVP2011-57611 313

    Development of Codes & Standards for ITER In-Vessel ComponentsDaniel Couso, Jose Fano, Felicidad Fernandez, Elena Fernandez, Julio A. Guirao,

    Jose L. Lastra, Victor J. Martinez, Javier Ordieres, and Ivan Vazquez

    HDPE PIPE AND RELATED ISSUES IN CODES AND STANDARDS

    Introduction 323

    PVP2011-57050 325

    A Historical Perspective of HDPE Piping Material DevelopmentWilliam Adams

    PVP2011-57904 335

    A Simplified Stress Intensity Factor Relation for Assessment of External Axial Flawed

    Safety-Related Nuclear Power Plant HDPE PipingS. Kalyanam, P. Krishnaswamy, M. Uddin, and D.-J. Shim

    PVP2011-57908 343

    Assessment of NDE Methods to Detect Lack of Fusion in HDPE Butt Fusion Joints

    Susan L. Crawford, Steven R. Doctor, Anthony D. Cinson, Michael W. Watts,Tract L. Moran, and Michael T. Anderson

    xii

  • HIGH TEMPERATURE CODES AND STANDARDS

    Introduction 351

    PVP2011-57074 353

    Simplified Analysis Methods for Primary Load Designs at Elevated TemperaturesPeter Carter, T.-L. (Sam) Sham, and Ft. I. Jetter

    PVP2011-57285 365

    The Creep-Fatigue Evaluation Method for Intermediate Hold Conditions:

    Proposal and ValidationSatoshi Okajima, Nobuchika Kawasaki, Shoichi Kato, and Naoto Kasahara

    PVP2011-57478 373

    Crack Initiation/Propagation of Perforated Plate Under Displacement-Controlled FatigueTest at Elevated TemperatureOsamu Watanabe, Taisuke Akiyama, and Akihiro Matsuda

    PVP2011-57585 383

    Thermal Fatigue Analysis at a Mixing Tee by a Fluid-Structural Simulation

    Masayuki Kamaya, Yoichi Utanohara, and Akira Nakamura

    PVP2011-57614 393

    Presentation of RCC-MRx Code 2010 for Sodium Reactors (SFR), Research Reactor (RR) and

    Fusion (ITER): General Overview and CEN-WorkshopT. Lebarbe, D. Hyvert, S. Marie, O. Gelineau, D. Bonne, and Frantz De La Burgade

    PVP2011-57620 401

    Presentation of FP7 MATTER Project: General OverviewT. Lebarbe, S. Marie, Pietro Agostini, Concetta Fazio, and Serguei Gavrilov

    PVP2011-57756 409

    High Temperature Design and Damage Evaluation of Mod. 9Cr-1Mo Steel Heat ExchangerHyeong-Yeon Lee, Jong-Bum Kim, Jae-Hyuk Eoh, Yong-Bum Lee, and Hong-Yune Park

    PVP2011-57843 417

    An Automatic Procedure for the Application of the Italian Standard for Creep-OperatedPressure Equipment

    Ottaviano Grisolia

    INTERACTION AND FLAW MODELING FOR MULTIPLE FLAWS

    Introduction 431

    PVP2011-57147 433

    Ductile Fracture Simulation of Mulitple Surface Flaws

    Kazuhiro Suga, Katsumasa Miyazaki, Ryotaro Senda, and Masanori Kikuchi

    PVP2011-57155 441

    Numerical Simulation of Coalescence Behavior of Multiple Surface Cracks

    Masanori Kikuchi, Yoshitaka Wada, Kazuhiro Suga, and Chikako Ohdama

    xiii

  • PVP2011-57188 , 447

    Study on the Interaction of Multiple Flaws in Ductile Fracture Process

    Kazuhiro Suga, Katsuma