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

Austenitic Stainless Steel

Rim Nayal and Hasan Charkas

PVP2009-78136 163

Dispelling the Myths Behind Regulatory Issue Summary 2008-30 (Nuclear Plant ComponentFatigue Sensitivity Analyses)

Terry J. Herrmann, Tyler D. Novotny, and Gary L. Stevens

x

INTERACTION AND MODELING FOR MULTIPLE FLAWS

Introduction 171

PVP2009-77068 173

Evaluation of Alignment Rules Using Stainless Steel Pipes With Non-Aligned Flaws

Kunio Hasegawa, Katsumasa Miyazaki, Koichi Saito, and Bostjan Bezensek

PVP2009-77073 181

Interaction Effect Analysis of Two Surface Cracks Using S-Version FEM

Masanori Kikuchi, Yoshitaka Wada, Hitomi Suyama, and Yulong Li

PVP2009-77103 187

Experimental Study of Ductile Fracture for Non-Aligned Multiple Flaws in a Plate

Katsumasa Miyazaki, Kunio Hasegawa, Koichi Saito, and Bostjan Bezensek

PVP2009-77338 199

A Flaw Proximity Rule for Interacting Surface Cracks Based on Elastic-Plastic

Fracture Analysis

Masayuki Kamaya

PVP2009-77402 207

A Numerical Study of the Alignment of Surface Flaws in a PipeBostjan Bezensek, Katsumasa Miyazaki, Kunio Hasegawa, and Koichi Saito

PVP2009-77717 215

Fracture Assessment of Austenitic Stainless Steel Piping With Twin Flaws in TIG Weld

Masao Itatani, Chihiro Narazaki, Takahiro Hayashi, Toshiyuki Saito, and Takuya Ogawa

PVP2009-77924 223

Experimental Estimation of Fully Plastic Collapse Stresses for Pipes With Three

Circumferential Flaws

Fuminori Iwamatsu, Katsumasa Miyazaki, Koichi Saito, and Kunio Hasegawa

PVP2009-78040 229

Growth Behavior of Two Interacting Surface Cracks of Dissimilar Size

Masayuki Kamaya, Masanori Kikuchi, and Eiichi Miyokawa

API 579/ASME CODE FITNESS-FOR-SERVICE ACTIVITIES

Introduction 235

PVP2009-77180 237

Technical Basis for Acceptance/Rejection Criteria for Flaws in High Pressure Gas CylinderMahendra D. Rana, John H. Smith, and Henry Holroyd

PVP2009-77483 247

Creep-Fatigue Interaction in Coke Drums: An Approach Based on

API 579-1/ASME FFS-1 2007

M. Sohel. M. Panwala, K. N. Srinivasan, and S. L. Mehta

xi

PVP2009-77606 255

Discussion on a Comparative Study Among FFS Rules

Kenji Oyamada, Shinji Konosu, and Takashi Ohno

PVP2009-77998 271

Determination of Fracture Arrest Stress

Jeremy C. Staats and David A. Osage

ASME CODE SECTION XI ACTIVITIES

Introduction 285

PVP2009-77061 287

Fracture Estimation Method for Pipe With Multiple Circumferential Surface Flaws

Yinsheng Li, Kunio Hasegawa, Kunio Onizawa, and Masayoshi Shimomoto

PVP2009-77132 297

Assessment of Piping Field Failures and Burst Tests on Carbon Steel Pipes With Local

Wall Thinning Using ASME Section XI Code Case N-597-2

Kunio Hasegawa, Toshiyuki Meshii, and Douglas A. Scarth

PVP2009-77178 307

Through Wall Repairs Using the GTAW Ambient Temperature Temperbead Process

Bruce Newton

PVP2009-77519 311

An Investigation of the Stress Intensity Factor Along a Corner Crack in Pressurizer Vent

Nozzle Penetration Weld

Sang-Min Lee, Jeong-Soon Park, Jin-Su Kim, Young-Hwan Choi, and Hae-Dong Chung

PVP2009-77613 317

A Residual Stress Analysis of a Corner Crack in Pressurizer Vent Nozzle Penetration Weld

Sang-Min Lee, Jeong-Soon Park, Young-Hwan Choi, Hae-Dong Chung, Doo-Ho Cho,Yoon-Suk Chang, and Young-Jin Kim

PVP2009-77824 323

Technical Basis for Revisions to ASME Section XI Acceptance Standards for Surface Flaws

in Piping in Stress Corrosion Cracking Susceptible Materials

Douglas A. Scarth, Katsumasa Miyazaki, Kunio Hasegawa, and Warren H. Bamford

PVP2009-77917 339

Stress Intensity Factors for Semi-Elliptical Surface Cracks With Flaw Aspect Ratio

Beyond the ASME XI Limit

Christian Malekian, Eric Wyart, Michael Savelsberg, Pierre-Eric Fouquet, Nicolas Minjauw,Audrey Wendling, and Anne Teughels

xii

RECENT DEVELOPMENTS IN ASME CODES AND STANDARDS

Introduction 353

PVP2009-77159 355

ASME B31.12 Hydrogen Piping and Pipeline Code Design Rules and Their Interaction With

Pipeline Materials Concerns, Issues and Research

Louis E. Hayden and Doug Stalheim

PVP2009-78101 363

Buckling of Cylindrical Thin Wall, Trailer Truck Tanks and ASME Section XII

Guido G. Karcher, Monte Ward, and Gary Spoelstra

PVP2009-78143 373

Procedural Assistance With Working Within ASME Code Case 2235-9

Alex McLay

RECENT DEVELOPMENTS IN JAPANESE CODES AND STANDARDS

Introduction 377

PVP2009-77062 379

Prediction of Failure Bending Moment for a Pipe With an Arbitrary-ShapedCircumferential Flaw

Yinsheng Li, Kunio Hasegawa, and Akira Shibuya

PVP2009 77601 387

Overview of the Revised J EAC4201-2007, Japanese Code of Surveillance Tests for

Reactor Vessel Materials

Takashi Hirano, Seiji Asada, Norimichi Yamashita, Masanobu Iwasaki, and

Minoru Tomimatsu

PVP2009-77624 395

Numerical Simulation of Irradiation-Induced Grain-Boundary Phosphorous Segregation in

Reactor Pressure Vessel Steels Using Rate Theory Model With First-Principles Calculations

Ken-ichi Ebihara, Masatake Yamaguchi, Yutaka Nishiyama, Kunio Onizawa, and

Hiroshi Matsuzawa

PVP2009-77658 403

Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement

Kenji Dohi, Kenji Nishida, Akiyoshi Nomoto, Naoki Soneda, Hiroshi Matsuzawa, and

Minoru Tomimatsu

PVP2009-77670 411

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

Yadong Wang, Yanting Xu, Bing Wang, Shoubao Ding, Jiele Xu, and Mulin Zheng

PVP2009-77577 453

Experimental Investigation on Flow Characteristics of Hydrogen in Pipelines

Jinyang Zheng, Honggang Chen, Ping Xu, Yongzhi Zhao, Lifang Zhang, and Yanlei Liu

PVP2009-77608 461

Comparison of the Strength Design and Prevention Method of Elephant Foot Buckling

Among Countries' Standards of Oil Tanks

Zhiping Chen, Bo Sun, Chulin Yu, Zhou Fang, and Ming Zeng

PVP2009-77627 467

Numerical Simulation on the Sound Field of Gas Valve Due to Inner Leakage

Bing Wang, Yadong Wang, Wenjun Liang, Shuiping Sheng, Jianping Guo, and

Liang Zhang

PVP2009-77843 473

Non-Linear Numerical Analysis on Large-Sized Double-Cone Sealing Process

Shui-ping Sheng, Shu-xin Han, Jin-yang Zheng, Yong-jian Gao, and Ning Zhou

PVP2009-77844 479

Research on Defects Examination and Crack Assessment for Cast Iron DryerShu-xin Han, Shui-ping Sheng, Ping Yu, Wei-zhong Li, Hai-yun Chen, and Qing Du

PVP2009-77875 485

Sound Source Location Error Analysis of Acoustic Emission Technique for Thick-Wall

Pressure Vessel InspectionFujun Liu, Shoubao Ding, Dongming Hu, Qiang Wang, Yanting Xu, Shuai Kong, and

Mulin Zheng

PVP2009-77978 493

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

Hideo Nakajima, Katsutoshi Takano, Fumiaki Tsutsumi, Katsumi Kawano,

Kazuya Hamada, and Kiyoshi Okuno

PVP2009-77639 799

JSME Construction Standard for Superconducting Magnet of Fusion Facility "Fabrication,

Installation, NDE and Testing"Masataka Nakahira, Kenichiro Niimi, and Hirosada Irie

PVP2009-77825 807

JSME Construction Standard for Superconducting Magnet of Fusion Facility "MATERIAL"

Arata Nishimura and Hideo Nakajima

xviii

PVP2009-77991 815

JSME Construction Standard for Superconducting Magnet of Fusion Facility "Procedure for

Structural Design"Yukio Takahashi, Shigeru Tado, Kazunori Kitamura, Masataka Nakahira, Junji Ohmori,

and Yuji Nakasone

PVP2009-78018 821

JSME Construction Standard for Superconducting Magnet of Fusion Facility:

General View of the Code

Yuji Nakasone, Yukio Takahashi, Arata Nishimura, Tetsuya Suzuki, Hirosada trie, and

Masataka Nakahira

CALVIN W. RICE LECTURE

PVP2009-77468 827

The Fabulous Nuclear Odyssey of BelgiumLuc H. Geraets

Author Index 837

xix