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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