Proceedings of the ASME Pressure Vessels and Piping Conference - 2009 - VOLUME 1 Codes and Standards presented at 2009 ASME PRESSURE VESSELS AND PIPING CONFERENCE JULY 26-30, 2009 PRAGUE, CZECH REPUBLIC sponsored by SSURE VESSELS AND PIPING DIVISION, ASME TECBNISCHE INFORMATIONSBIBLIOTHEK UNIVERSITATSBIBLIOTHEK HANNOVER PR ASME Three Park Avenue New York, N.Y. 10016
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Proceedings of the
ASME Pressure Vessels
and Piping Conference
- 2009 -
VOLUME 1
Codes and Standards
presented at
2009 ASME PRESSURE VESSELS AND PIPING CONFERENCE
JULY 26-30, 2009
PRAGUE, CZECH REPUBLIC
sponsored by
SSURE VESSELS AND PIPING DIVISION, ASME
TECBNISCHEINFORMATIONSBIBLIOTHEK
UNIVERSITATSBIBLIOTHEK.
HANNOVER PR
ASME
Three Park Avenue New York, N.Y. 10016
CONTENTS
CODES AND STANDARDS
STRUCTURAL INTEGRITY OF PRESSURE COMPONENTS
Introduction 1
PVP2009-77145 3
J-Based Failure Assessment Diagrams for Axially Cracked Pipes Under Pressure
Graham Chell, Brian Gardner, Chong Rhee, and Pedro Vargas
PVP2009-77421 15
Flaw Tolerance Evaluation of CASS Piping Materials
Timothy J. Griesbach, Vikram Marthandam, Haiyang Qian, and Patrick O'Regan
PVP2009-77609 21
A Comparison of Fracture Assessment Methods in Several Structural Integrity Assessment
Procedures
Tiecheng Yang, Xuedong Chen, and Zhichao Fan
PVP2009-78134 31
Study on Strain Rate Effect on Dynamic Strain Aging and Safety Margin of Pipe Elbow at
Seismic Event
Hiro Kobayashi and Yoshio Urabe
ELASTIC-PLASTIC ANALYSIS ACCORDING TO
2007 SECTION VIII-DIVISION 2 RULES
Introduction 39
PVP2009-77394 41
Investigation of the Elastic-Plastic Design Method in Section VIII Div. 2
Wolf Reinhardt
PVP2009-77838 51
Weight Savings Using ASME Section VIII, Division 2, Design-by-Analysis Methods
Kanhaiya L Bardia, Donold G. LaBounty, Michael M. Basic, and Timothy D. Breig
PVP2009-77856 57
An Appraisal of Two Simplified Inelastic Methods of the ASME Code
Somnath Chattopadhyay
PVP2009-77859 69
Fatigue Analysis Methods: Their Performance Evaluation for a Class of Pressure Vessels
With Welded Joints
Arturs Kalnins
ix
RATCHETING ISSUES IN PRESSURE VESSELS DESIGN
Introduction 79
PVP2009-77474 81
A Hybrid Procedure for Ratchet Boundary Prediction
Michael Martin and David Rice
PVP2009-77766 89
Ratcheting Predictive Methods in RCC-MR Code
Odile Gelineau, Morello Sperandio, and Marie-Noel Berton
PVP2009-77813 95
Residual Stress and Strain Responses of Welded Piping Joints Under Low-Cycle
Fatigue LoadingPei-Yuan Cheng and Tasnim Hassan
PVP2009-77819 103
Simulation of Ratcheting Responses of Elbow Piping ComponentsTasnim Hassan and Syed M. Rahman
PVP2009-77863 109
Shakedown/Ratcheting Boundary Determination Using Iterative Linear Elastic Schemes
R. Adibi-Asl and W. Reinhardt
ENVIRONMENTAL FATIGUE ISSUES
Introduction 121
PVP2009-77077 123
Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation
Method for Nuclear Power Plants in JSME Code
Makoto Higuchi, Takao Nakamura, and Yasuaki Sugie
PVP2009-77115 133
Optimization of Environmental Fatigue Evaluation (Step 2)Yuichirou Nomura, Kazuya Tsutsumi, Toshihide Inoue, Seiji Asada, and Takao Nakamura
PVP2009-77558 145
Proposal for Determination of Strain Rate in Environmental Fatigue Correction Evaluation
Seiji Asada
PVP2009-78124 153
Comparison of Component Fatigue Test Data With Proposed EAF Methodologies for
Study on Factors Important to Structural Integrity of Reactor Pressure Vessel During PTS
With Regard to Fracture ProbabilityKunio Onizawa and Hiroshi Matsuzawa
PVP2009-77720 419
Evaluation of Fracture Characteristics of Ni-Base Weld Metal for BWR ComponentsMasao Itatani, Toshiyuki Saito, Takahiro Hayashi, Chihiro Narazaki, Kazuo Ogawa, and
Masaaki Kikuchi
xiii
PVP2009-78096 429
Prediction of Radiation Embrittlement for Highly Irradiated Reactor Pressure Vessel Steels
Hiroshi Matsuzawa
PVP2009-78103 435
Microstrucutural Characteriazation of RPV Steels Irradiated to High Fluences
Minoru Tomimatsu, Hiroyuki Sakamoto, Kenji Dohi, Toshiyuki Watanabe, and
Hiroshi Matsuzawa
RECENT DEVELOPMENTS IN CHINESE CODES AND STANDARDS
Introduction 445
PVP2009-77444 447
Research on Metal Atmospheric Storage Tank Inspection Method for Standard in China
Effects of Axial and Radial Distortion on Residual Stress of HSAW Pipe
Qingren Xiong, Wenzhen Zhao, Maosheng Zheng, Yaorong Feng, Lingkang Ji, and
Feng Hu
xiv
RECENT DEVELOPMENTS IN EUROPEAN AND INTERNATIONAL
CODES AND STANDARDS
Introduction 499
PVP2009-77119 501
Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects:Improvement of the Leak-Before-Break Procedure and Related Defect Assessment Tools
S. Marie, Y. Kayser, B. Drubay, M. Nedelec, C. Delaval, H. Deschanels, and M. Sperandio
PVP2009-77144 511
International Standards for Boilers and Pressure Vessels
Stuart Cameron and Richard (Gene) Feigel
PVP2009-77273 519
Cross Comparison of European and American Pressure Vessel Standards in the Designof the Main Pressure Vessel Components
Fernando Lidonnici
PVP2009-77840 531
New Russian National Standards on Pressure Vessel and Apparatus Design and
Strength Calculation
Boris Volfson
PVP2009-77919 537
Strength Assessment of Equipments and Piping of WWER Nuclear Power Plants
Stanislav Vejvoda
PVP2009-78036 543
An Overview of QA/QC Requirements in Present NPP Projects
Philippe Malouines
PVP2009-78046 549
Adaptation of RCC-M Design and Construction Rules to the Evolution of Projects Needs,
Regulatory Evolutions and International ExchangesJean-Marie Grandemange
PVP2009-78057 555
BS 7910: History and Future DevelopmentsIsabel Hadley
HIGH TEMPERATURE CODES AND STANDARDS
Introduction 565
PVP2009-77120 567
Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects:
Improvement of the Creep Fatigue Rules
Marie Noel Berton, Olivier Ancelet, Odile Gelineau, and Morello Sperandio
xv
PVP2009-77232 573
A Comparative Study of Negligible Creep Curves for Rational Elevated Temperature DesignMasanori Ando, Nobuhiro Isobe, Nobuchika Kawasaki, Masayuki Sukekawa, and
Naoto Kasahara
PVP2009-77406 583
ASME Code Needs for Very High Temperature Generation IV Reactors
William J. O'Donnell and Donald S. Griffin
PVP2009-78130 603
Recent Developments in High Temperature CodesBilal Dogan and R. A. Ainsworth
REPAIR, REPLACEMENT AND MITIGATION FOR
FITNESS-FOR-SERVICE RULES
Introduction 613
PVP2009-77112 615
Study on Requirements to be Fulfilled With Rules for Repair Replacement Activities in
JSME Code on Fitness-For-Service
Akira Nishikawa, Koji Dozaki, Koji Koyama, and Kazuyuki Asada
PVP2009-77135 621
Prediction of Plastic Collapse Moments for Circumferential Cracked Pipes With
Weld OverlaysKunio Hasegawa, Yinsheng Li, Gery M. Wilkowski, and Arthur F. Deardorff
PVP2009-77344 629
Stress Corrosion Cracking in Welds of Reactor Vessel Nozzle at Ohi-3 and of Other Vessel's
Nozzle at Japan's PWR Plants
Takao Nakamura, Keiji Taniguchi, Shinro Hirano, Narita Marekazu, and Tomonobu Sato
PVP2009-77901 639
Development of Stress Reduction Method in the Pipe Welded Zone
Yuka Fukuda, Osamu Saito, Satoru Aoike, and Fuminori Iwamatsu
PROBABILISTIC AND RISK BASED ASSESSMENT FOR
CODES AND STANDARDS
Introduction 647
PVP2009-77186 649
Validity of Successive Inspections to the Piping With Multiple Circumferential Stress
Corrosion Cracks
Hideo Machida
PVP2009-77349 657
Reliability Assessment of Piping With Cracks Using Advanced First-Order
Second-Moment Method
Shinji Yoshida and Hideo Machida
xvi
PVP2009-77401 665
Development and Application of a Streamlined RI-ISI MethodologyPatrick O'Regan
PVP2009-77778 671
A Risk-Informed Methodology for ASME Section XI, Appendix G
Ronald Gamble, William Server, Bruce Bishop, Nathan Palm, and Carol Heinecke
PVP2009-77904 687
Failure Assessment of Nuclear Piping Components Due to Combined DegradationMechanisms by an Advanced Probabilistic Fracture Mechanics Code
Debashis Datta and Changheui Jang
INNOVATIVE CONCEPTS FOR NEXT GENERATION
CODES AND STANDARDSIntroduction 695
PVP2009-77333 697
Methodology for the Determination of a Set of Safety Factors That are Consistent for
Design Code and Fitness-for-Service Code: Framework
Tai Asayama
PVP2009-77686 705
Methodology for the Determination of a Set of Safety Factors That are Consistent for
Design Code and Fitness-for-Service Code: Case Study for Fast Breeder Reactors
Tai Asayama
PVP2009-77705 711
Creep-Fatigue Life Determination of Grade 91 Steel Using a Strain-Range
Separation Method
Wolfgang Hoffelner
PVP2009-77953 717
The Impact of Material and Design Criteria on the Assessment of Negligible Creep
Robert I. Jetter, T.-L (Sam) Sham, and Robert W. Swindeman
PVP2009-77984 727
Development of a Material Strength Standard for Japanese Demonstration
Fast Breeder Reactor
Takashi Onizawa, Yuji Nagae, Takashi Wakai, and Tai Asayama
MATERIALS, WELDING, DESIGN AND RESIDUAL LIFE OF
CZECH A.M.E. CODES
Introduction 735
PVP2009-77288 737
Ensuring Integrity of High Energy Piping in the NPP's of the Czech RepublicJiri Zdarek, Jan Dotrel, and Vaclav Jarolimek
xvii
PVP2009-77392 745
VERL1FE Unified Procedure for Lifetime Assessment of Components and Piping in WWER
NPPs During Operation: Updating and Further DevelopmentMilan Brumovsky
PVP2009-77539 751
Material Selection Methodology Used in Czech NPP
Karel Matocha
PVP2009-77653 755
Safety Approach and Ageing Management in Czech Rules and Standards
Jaroslav Bartonicek, Junek Lubomir, Milan Vrana, and Stanislav Vejvoda
PVP2009-77918 763
History of A.M.E. Standard Creation
Stanislav Vejvoda
STRUCTURAL INTEGRITY OF FUSION REACTOR COMPONENTS
Introduction 769
PVP2009-77118 ,771
Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects:General Overview
S. Marie, B. Drubay, M. N. Berton, 0. Gelineau, C. Escaravage, D. Bonne, and
M. Sperandio
PVP2009-77337 779
JSME Construction Standard for Superconducting Magnet of Fusion Facility
"Quality Assurance"
Tetsuya Suzuki, Arata Nishimura, and Hideo Nakajima
PVP2009-77478 783
Progress in ITER Project and its Superconducting Magnet System in Japan
Kiyoshi Okuno, Hideo Nakajima, Yoshikazu Takahashi, and Norikiyo Koizumi
PVP2009-77553 789
Qualification of Cryogenic Structural Materials for the ITER Toroidal Field Coils