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ASME/JSME 2004 Pressure Vessels and Piping Conference

July 25–29, 2004

San Diego, California, USA

Conference Sponsors:

ISBN:

0-7918-4675-X

In This Volume

Pressure Vessel and Piping Codes and Standards

Finite Element Modelling of Fatigue Damage Using a Continuum Damage Mechanics Approach

A. M. P. De Jesus, A. S. Ribeiro, A. A. Fernandes

PVP 2004; 3-12https://doi.org/10.1115/PVP2004-2667

Abstract

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Topics: Damage mechanics , Fatigue damage , Finite element analysis , Modeling , Fatigue , Plasticity , Kinematics , Cycles , Steel , Computer simulation

Fatigue Analysis in Pressure Vessel Design by Local Strain Approach: Methods and Software Requirements

Arturs Kalnins

PVP 2004; 13-21https://doi.org/10.1115/PVP2004-2668

Abstract

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Topics: Computer software , Design , Fatigue analysis , Pressure vessels , Stress , Cycles , Stress-strain curves

Design Criteria for Biaxial/Multiaxial Low Cycle Fatigue

Takamoto Itoh, Masao Sakane, Takahiro Hata

PVP 2004; 23-30https://doi.org/10.1115/PVP2004-2669

Abstract

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Topics: Design , Low cycle fatigue , Damage , Fatigue , Flow (Dynamics) , Hardening , Structural elements (Construction)

Life Prediction for Notched Components in Nonproportional Low Cycle Fatigue: Experiment and FEM Analysis

Masao Sakane, Tsuneo Itoh, Tomoshige Susaki, Yoshiyasu Kawazoe

PVP 2004; 31-38https://doi.org/10.1115/PVP2004-2670

Abstract

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Topics: Finite element methods , Finite element model , Low cycle fatigue , Fracture (Materials) , Finite element analysis , Stainless steel , Tension , Torsion

Transitional Behavior of Residual Fatigue Life After Applying Overload During Fatigue Crack Growth With Constant Stress Amplitude

Anindito Pumowidodo, Tatsujiro Miyazaki, Chobin Makabe, Arthur J. McEvily

PVP 2004; 39-44https://doi.org/10.1115/PVP2004-2671

Abstract

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Topics: Fatigue cracks , Fatigue life , Stress , Crack propagation , Fracture (Materials)

A Method of Detecting Fatigue Crack Initiation and an Application of an Overload Using Local Strains

Chobin Makabe, Hideo Kaneshiro

PVP 2004; 45-51https://doi.org/10.1115/PVP2004-2672

Abstract

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Topics: Fatigue cracks , Fracture (Materials) , Stress , Crack propagation , Cycles , Shapes

Plastic Loads for Internally Pressurized Toroidal Shells

J. Blachut

PVP 2004; 53-59https://doi.org/10.1115/PVP2004-2673

Abstract

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Topics: Pressure , Shells , Steel , Stress , Fracture (Materials) , Nozzles , Wall thickness , Welded joints , Welding

Fatigue Crack Growth Curve for Austenitic Stainless Steels in PWR Environment

Yuichiro Nomura, Kazuya Tsutsumi, Hiroshi Kanasaki, Naoki Chigusa, Kazuhiro Jotaki, Hidetaka Shimizu, Takashi Hirose, Hitoshi Ohata

PVP 2004; 63-70https://doi.org/10.1115/PVP2004-2674

Abstract

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Topics: Fatigue cracks , Pressurized water reactors , Stainless steel , Boiling water reactors , Stress , Fatigue testing , Japan Society of Mechanical Engineers , Temperature , Water

Fatigue Crack Propagation Tests on 304 Stainless Steel in High Temperature Water: Accelerated Cracking Rates and Transition to Lower Rates

G. L. Wire, W. M. Evans, W. J. Mills

PVP 2004; 71-81https://doi.org/10.1115/PVP2004-2675

Abstract

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Topics: Fatigue cracks , Fracture (Process) , High temperature , Stainless steel , Water , Heat , Stress , Hydrogen , Wire , Crack propagation

Corrosion Fatigue Behavior of Low-Alloy Pressure Vessel Steels in High Temperature Water Under Multi-Factor Conditions

Xinqiang Wu, Yasuyuki Katada

PVP 2004; 83-90https://doi.org/10.1115/PVP2004-2676

Abstract

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Topics: Alloys , Corrosion , Fatigue , High temperature , Pressure vessels , Steel , Water , Sulfur , Temperature , Coolants

The Incorporation of a Fatigue Threshold Concept Into a Known Superposition Crack Growth Model for Alloy 690 in High Temperature, Low Oxygen Water

Bruce A. Young

PVP 2004; 91-94https://doi.org/10.1115/PVP2004-2677

Abstract

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Topics: Alloys , Fatigue , Fracture (Materials) , High temperature , Oxygen , Water , Cycles , Pressurized water reactors , Corrosion , Fatigue cracks

Evaluation of Environmental Effects on the Fatigue of Notched Specimen of Austenitic Stainless Steel Using Modified Rate Approach Method

Katsumi Sakaguchi, Yasuhide Asada, Masao Itatani, Toshiyuki Saito

PVP 2004; 95-99https://doi.org/10.1115/PVP2004-2678

Abstract

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Topics: Fatigue , Stainless steel , Fatigue life , Fatigue testing , High temperature , Water , Stress concentration , Elastic moduli , Finite element methods , Finite element model

The Modified Rate Approach Method to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water in Austenitic Stainless Steel

Yuichiro Nomura, Makoto Higuchi, Yasuhide Asada, Katsumi Sakaguchi

PVP 2004; 101-108https://doi.org/10.1115/PVP2004-2679

Abstract

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Topics: Fatigue life , Stainless steel , Temperature , Water , Light water reactors , Fatigue damage , Steel , Transients (Dynamics)

Effects of Water Flow Rate on Fatigue Life of Carbon and Stainless Steels in Simulated LWR Environment

Akihiko Hirano, Michiyoshi Yamamoto, Katsumi Sakaguchi, Tetsuo Shoji

PVP 2004; 109-119https://doi.org/10.1115/PVP2004-2680

Abstract

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Topics: Carbon , Fatigue life , Flow (Dynamics) , Light water reactors , Stainless steel , Water , Sulfur , Corrosion , Fatigue , Fatigue testing

Effect of Hydrogenated Water on Fatigue Crack Growth for Austenitic Stainless Steel in Simulated BWR Water Environment

Li H. Wang

PVP 2004; 121-128https://doi.org/10.1115/PVP2004-2681

Abstract

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Topics: Boiling water reactors , Fatigue cracks , Stainless steel , Water , Fracture (Materials) , Water chemistry , Electrolytic corrosion , Fatigue , Fractography , Hydrogen

Evaluation of Fatigue Damage on Operating Plant Components in LWR Water

Makoto Higuchi, Takashi Hirano, Katsumi Sakaguchi

PVP 2004; 129-138https://doi.org/10.1115/PVP2004-2682

Abstract

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Topics: Fatigue damage , Light water reactors , Water , Temperature , Fatigue , Cycles , Stress , Transients (Dynamics) , Alloys , Carbon

Design Issues and Considerations During Reactor Vessel Head Replacement, Steam Generator Replacement, and Steam Generator Snubber Elimination at Nuclear Power Plants

Dilip Bhavnani, James Annett

PVP 2004; 141-148https://doi.org/10.1115/PVP2004-2683

Abstract

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Topics: Boilers , Design , Nuclear power stations , Reactor vessels , Licensing , Pressurized water reactors , Steam , Containment , Maintenance , Nuclear reactor coolants

Code Compliance of a PWR Charging Line Nozzle

Daniel J. Vasquez, Nitin J. Shah, Keshab K. Dwivedy

PVP 2004; 149-155https://doi.org/10.1115/PVP2004-2684

Abstract

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Topics: Nozzles , Pressurized water reactors , Design , Transients (Dynamics) , Licensing , Accounting , ASME Standards , Fatigue , Fatigue analysis , Flow (Dynamics)

A Parametric Study of ASME B16.5 Flanges Which Has Experienced Flange Face Corrosion

C. Nadarajah

PVP 2004; 157-163https://doi.org/10.1115/PVP2004-2685

Abstract

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Topics: Corrosion , Flanges , Finite element methods , Fittings , Pipes , Piping systems

Finite Element Analysis of a Slab Tank

Yogeshwar Hari

PVP 2004; 165-172https://doi.org/10.1115/PVP2004-2686

Abstract

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Topics: Finite element analysis , Slabs , Stress , Pressure , Design , Flat plates , Deflection , Computer software , Dimensions , Plates (structures)

Analysis of a Hemispherical Head With Nozzle and Local Thin Area

Michael W. Guillot, Jack E. Helms

PVP 2004; 173-175https://doi.org/10.1115/PVP2004-2687

Abstract

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Topics: Nozzles , Finite element analysis , Finite element model , Plasticity , Pressure vessels , Stress

Integrity Assessment of Pressure Components With Local Hot Spots

R. Seshadri

PVP 2004; 177-185https://doi.org/10.1115/PVP2004-2688

Abstract

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Topics: Pressure , Catalysts , Design , Engineering standards , Fitness-for-service , Flow (Dynamics) , Linings (Textiles) , Piping systems , Pressure vessels , Vessels

B₂' Stress Indices for Elbows Using Non-Linear Finite Element Analysis

K. Venkataramana, V. Bhasin, K. K. Vaze, H. S. Kushwaha

PVP 2004; 187-194https://doi.org/10.1115/PVP2004-2689

Abstract

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Topics: Finite element analysis , Stress , Collapse , Deformation , Nuclear power stations , Earthquakes , Hardening , ASME Standards , Boilers , Damage

Outline of the JSME (Japan Society of Mechanical Engineers) Rules on Design and Construction for Nuclear Power Plants

Itaru Saito, Takashi Shimakawa

PVP 2004; 197-204https://doi.org/10.1115/PVP2004-2690

Abstract

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Topics: Construction , Design , Japan Society of Mechanical Engineers , Nuclear power stations , Boilers , Governments , JSME Standards , Pressure vessels

Outline of the JSME Rules on Design and Construction for Thermal Power Generation Facilities

Isoharu Nishiguchi, Masaaki Fujita, Seiichi Hamada

PVP 2004; 205-209https://doi.org/10.1115/PVP2004-2691

Abstract

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Topics: Construction , Design , Japan Society of Mechanical Engineers , Thermal energy , Energy generation , JSME Standards , Boilers , Economics , Pressure vessels

JSME Code on Protection Design Against Postulated Pipe Rupture for Nuclear Power Plants

Keisuke Kitsukawa, Hiroshi Yokota, Koichi Murayama, Hiroshi Ueda, Yasukazu Takada, Hideo Kobayashi

PVP 2004; 211-215https://doi.org/10.1115/PVP2004-2692

Abstract

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Topics: Design , JSME Standards , Nuclear power stations , Pipes , Rupture , Japan Society of Mechanical Engineers , Alloys , Carbon steel , Containment vessels , Energy generation

First Publication of the Nuclear Materials Code for Nuclear Facilities in Japan

Hiroyoshi Murakami

PVP 2004; 217-219https://doi.org/10.1115/PVP2004-2693

Abstract

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Topics: Nuclear power stations , Engineering standards , Japan Society of Mechanical Engineers , Boilers , Construction , Design , Economics , JSME Standards , Pressure vessels , Thermal energy

Implementation of Regulatory Rules on Fitness-for-Service for Nuclear Power Plants in Japan

Takehiko Nakamura, Tetsuya Yamamoto, Iwao Oshima, Kiyoshi Takasaka, Yukio Hirano, Eiji Hiraoka

PVP 2004; 221-225https://doi.org/10.1115/PVP2004-2694

Abstract

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Topics: Fitness-for-service , Nuclear power stations , Engineering standards , In-service inspection , Japan Society of Mechanical Engineers , Mechanical engineers , Nondestructive evaluation , Safety

Current Status of Japanese Code on Fitness-for-Service for Nuclear Power Plants

Koichi Kashima, Tomonori Nomura, Koji Koyama

PVP 2004; 227-234https://doi.org/10.1115/PVP2004-2695

Abstract

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Topics: Fitness-for-service , Nuclear power stations , Japan Society of Mechanical Engineers , ASME Standards , Boiling water reactors , In-service inspection , Inspection , Maintenance , Pipes , Pressure vessels

Study on Flaw Acceptance Standard of ASME Code Sec. XI Based on Failure Probability

Katsuyuki Shibata, Kunio Onizawa, YinSheng Li, Yasuhiro Kanto, Shinobu Yoshimura

PVP 2004; 235-242https://doi.org/10.1115/PVP2004-2696

Abstract

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Topics: Acceptance criteria , ASME Standards , Failure , Probability , Fracture (Materials) , Fracture (Process) , Reactor vessels , Shapes , Stress , Thermal shock

Application of Potential Drop Technique to the Inspection of Welded Boiler Pressure Parts

Seiichi Hamada, Yasuki Ogawa, Hideo Iida, Tomoki Kuroiwa, Masahiko Kuroki, Manabu Hayakawa

PVP 2004; 243-246https://doi.org/10.1115/PVP2004-2697

Abstract

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Topics: Boilers , Inspection , Pressure , Power Piping Code , Creep , Damage , Direct current potential drop techniques , Pipes , Electrical potential drop techniques , Electricity (Physics)

Reliability Assessment of Piping in a Nuclear Power Plant Considering Flaw Detection Probability

Hideo Machida, Norimichi Yamashita, Shinobu Yoshimura, Genki Yagawa

PVP 2004; 247-254https://doi.org/10.1115/PVP2004-2698

Abstract

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Topics: Flaw detection , Nuclear power stations , Pipes , Probability , Reliability , Fracture (Materials) , Inspection , Boiling water reactors , Cracking (Materials) , Failure

What’s New in Section I [2001 Through 2003]

John R. MacKay

PVP 2004; 257-259https://doi.org/10.1115/PVP2004-2699

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , Boilers , Heat recovery steam generators , Maintenance , Pressure vessels

What’s New in ASME Section II, Materials, 2004

Michael Gold

PVP 2004; 261-263https://doi.org/10.1115/PVP2004-2700

Abstract

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Topics: Construction

What’s New in Section XI (Welding)

Joel G. Feldstein

PVP 2004; 265-268https://doi.org/10.1115/PVP2004-2701

Abstract

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Topics: Welding , Manufacturing , Boilers , Brazing , Design , Pipes , Pressure vessels

Application Experiences of ASME Section III Code in Korea

Sung Pyo Choi, Nam Ha Kim

PVP 2004; 269-275https://doi.org/10.1115/PVP2004-2702

Abstract

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Topics: ASME Standards , Construction , Design , Electricity (Physics) , Engineering standards

What’s New in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components

Gary Park

PVP 2004; 277-280https://doi.org/10.1115/PVP2004-2703

Abstract

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Topics: In-service inspection , Nuclear power stations , Inspection , Maintenance , Mechanical engineering , Nondestructive evaluation , Nuclear industry

What’s New in Section VIII [2002 Through 2003]

Thomas P. Pastor

PVP 2004; 281-284https://doi.org/10.1115/PVP2004-2704

Abstract

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Topics: Boilers , Maintenance , Pressure vessels

Comparative Study: EN 13445/ASME Section VIII Div. 1 & 2

Reinhard Preiss, Josef L. Zeman

PVP 2004; 285https://doi.org/10.1115/PVP2004-2705

Abstract

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Topics: Engineering standards

Background and Summary of Revisions to Appendix M of ASME Section VIII, Division 1: Stop Valves Located in the Pressure Relief Path

Richard J. Basile, Clay D. Rodery

PVP 2004; 287-293https://doi.org/10.1115/PVP2004-2706

Abstract

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Topics: Pressure , Valves , Pressure vessels , Petrochemicals , ASME Boiler and Pressure Vessel Code , Inspection , Maintenance , Overpressure protection , Pressure relief devices , Relief valves

Technical Changes in ASME B31.3, 2004 Edition

Charles Becht, IV

PVP 2004; 295-298https://doi.org/10.1115/PVP2004-2707

Abstract

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Topics: Process piping

Technical Basis for Equations for Stress Intensity Factor Coefficients in ASME Section XI Appendix A

Russell C. Cipolla, Darrell R. Lee

PVP 2004; 301-312https://doi.org/10.1115/PVP2004-2708

Abstract

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Topics: Stress , Computation , Fracture (Materials) , Surface cracks , Computer programming languages , Fittings , Flat plates , Geometry , Interpolation , Polynomials

Background and Technical Basis for the Evaluation of Flaws in PWR Reactor Vessel Head Penetration Regions

Warren Bamford, Guy De Boo

PVP 2004; 313-333https://doi.org/10.1115/PVP2004-2709

Abstract

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Topics: Pressurized water reactors , Reactor vessels , Acceptance criteria , Inspection , Leakage , Fracture (Materials) , Fracture (Process) , Geometry , Plant design , Shapes

Technical Basis for Acceptance of Flaws in Moderate Energy Class 2 and 3 Vessels and Tanks

Pat L. Strauch, Warren H. Bamford, Jr., Sushil K. Daftuar

PVP 2004; 335-340https://doi.org/10.1115/PVP2004-2710

Abstract

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Topics: Vessels , Leakage , Inspection , Acceptance criteria , ASME Standards , Failure , Fracture (Materials) , Pipes , Stress corrosion cracking , Surveillance

Validation of Pipe Flaw Evaluation Procedures in Section XI of the ASME Code Against Pipe Fracture Experiments

Phuong H. Hoang, Gery M. Wilkowski

PVP 2004; 341-347https://doi.org/10.1115/PVP2004-2711

Abstract

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Topics: ASME Standards , Fracture (Materials) , Fracture (Process) , Pipes , Acceptance criteria , Fracture mechanics , Stress , ASME Boiler and Pressure Vessel Code , Brittle fracture , Collapse

Failure Stresses for Pipes With Multiple Circumferential Flaws

Kunio Hasegawa, Hideo Kobayashi

PVP 2004; 351-355https://doi.org/10.1115/PVP2004-2712

Abstract

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Topics: Failure , Pipes , Stress , Stainless steel , Collapse , ASME Standards , Fracture (Materials) , Fracture (Process) , Fracture toughness , In-service inspection

Experimental Study for Proximity Rule of Multiple Flaws for Ductile Fracture

Katsumasa Miyazaki, Kunio Hasegawa, Takeshi Shimamura

PVP 2004; 357-363https://doi.org/10.1115/PVP2004-2713

Abstract

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Topics: Ductile fracture , Stress , Fracture (Materials) , Fracture (Process) , Brittle fracture , Carbon steel , Collapse , Flat plates , Pipes , Shapes

Seismic Loads for Crack Stability Assessment in a Review of Lead-Before-Break (LBB) Applicability

Norimichi Yamashita, Hideo Machida, Shinobu Yoshimura, Genki Yagawa

PVP 2004; 365-372https://doi.org/10.1115/PVP2004-2714

Abstract

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Topics: Fracture (Materials) , Stability , Stress , Earthquakes , Coolants , Leakage , Pipes , Design , Crack propagation , Boiling water reactors

Main Surface Crack Propagation and Crack Initiation and Propagation on Counter Plain Surface Under Cyclic Bending

Jin’ichiro Gotoh, Saburo Usami, Hiroshi Morita

PVP 2004; 373-378https://doi.org/10.1115/PVP2004-2715

Abstract

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Topics: Fracture (Materials) , Surface cracks , Crack propagation , Stress , Finite element analysis , Numerical analysis , Tension

Fracture and Deformation Behaviors of Tee Pipe With Local Wall Thinning Under Monotonic Bending

Koji Takahashi, Kotoji Ando, Masakazu Hisatsune, Kunio Hasegawa

PVP 2004; 381-386https://doi.org/10.1115/PVP2004-2716

Abstract

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Topics: Deformation , Fracture (Materials) , Pipes , Fracture (Process) , Buckling , Compressive stress , Corrosion , Erosion , Finite element methods , Metals

Allowable Limit and Finite Element Analysis of Pipes With Local Wall Thinning Subjected to Bending Moment

Seok Hwan Ahn, Ki Woo Nam, Koji Takahashi, Kotoji Ando

PVP 2004; 387-392https://doi.org/10.1115/PVP2004-2717

Abstract

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Topics: Finite element analysis , Pipes , Fracture (Materials) , Fracture (Process) , Failure mechanisms , Buckling , Carbon steel , Coolants , Finite element methods , Flow (Dynamics)