Volumes | Pressure Vessels and Piping Conference | American Society of Mechanical Engineers Digital Collection

Topics: Pipes , Stress , Failure , ASME Standards , Ductile fracture , Fracture toughness , Fracture (Materials) , Fracture (Process) , Fracture mechanics

Proximity Rules for Subsurface Transforming to Surface Flaws for Class 1 Ferritic Vessels

Kunio Hasegawa, Katsumasa Miyazaki, Douglas A. Scarth, Russell C. Cipolla

PVP 2006; 11-18doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93102

Abstract

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Topics: Vessels , Acceptance criteria

Stress Intensity Factor Solution for Subsurface Flaw Estimated by Influence Function Method

Katsumasa Miyazaki, Fuminori Iwamatsu, Shin Nakanishi, Masaki Shiratori

PVP 2006; 19-36doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93138

Abstract

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Topics: Stress , Polynomials , Fracture (Materials) , ASME Boiler and Pressure Vessel Code , Brittle fracture , Fatigue cracks , Fracture mechanics , Geometry , Residual stresses , Stress concentration

Supplementary Technical Basis for ASME Section XI Code Case N-597-2

Douglas A. Scarth, Kunio Hasegawa, Lee F. Goyette, Phil Rush

PVP 2006; 37-51doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93278

Abstract

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Topics: Acceptance criteria , ASME Boiler and Pressure Vessel Code , Construction , Corrosion , Design , Flow (Dynamics) , Mechanical engineers , Nuclear power stations , Pipes , Pressure

Technical Basis for Proposed Revisions to ASME Code Case N-513 and Some Applications to Moderate Energy Piping

Robert O. McGill, Nathaniel G. Cofie, Russell C. Cipolla, Guy DeBoo

PVP 2006; 53-60doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93428

Abstract

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Topics: ASME Standards , Pipes , Safety

Use of Class 1 Analysis to Aid Inservice Inspection

Daniel J. Vasquez, Nitin J. Shah

PVP 2006; 61-65doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93451

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Topics: In-service inspection , Inspection , Surges , Nozzles , Pipes , Rupture , Alloys , Bolted joints , Stress , Stress analysis (Engineering)

Net Section Plastic Collapse Analysis of Two-Layered Materials and Application to Weld Overlay Design

Arthur F. Deardorff, Nathaniel G. Cofie, David G. Dijamco, Aparna Chintapalli

PVP 2006; 67-75doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93454

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Topics: Collapse , Design , Overlays (Materials engineering) , Stress , Pipes , Fracture toughness , Maintenance , Boiling water reactors , Pressurized water reactors , Thermal expansion

Technical Basis for Revision of Inspection Requirements for Regenerative and Residual Heat Exchangers

Warren Bamford, Bruce Bishop, Richard Haessler, Mark Bowler

PVP 2006; 77-89doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93892

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Topics: Heat exchangers , Inspection , Construction , Cycles , In-service inspection , Irradiation (Radiation exposure) , Nuclear power stations , Nuclear reactor coolants , Optical quality control , Pressurized water reactors

Environmental Fatigue Initiation and Crack Growth

Revised and New Proposal of Environmental Fatigue Life Correction Factor (F_en) for Carbon and Low-Alloy Steels and Nickel Base Alloys in LWR Water Environments

Makoto Higuchi, Katsumi Sakaguchi, Akihiko Hirano, Yuichiro Nomura

PVP 2006; 93-102doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93194

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Topics: Alloys , Carbon , Fatigue life , Light water reactors , Nickel , Steel , Water , Fatigue , Oxygen , Sulfur

Effect of Factors on Fatigue Life in PWR Water Environment

Katsumi Sakaguchi, Yuichiro Nomura, Shigeki Suzuki, Kazuya Tsutsumi, Hiroshi Kanasaki, Makoto Higuchi

PVP 2006; 103-111doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93217

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Topics: Fatigue life , Pressurized water reactors , Water , Temperature , Alloys , Base metals , Carbon , Fatigue , Fatigue testing , Flow (Dynamics)

Applicability of the Modified Rate Approach Method Under Various Conditions Simulating Actual Plant Conditions

Katsumi Sakaguchi, Yuichiro Nomura, Shigeki Suzuki, Hiroshi Kanasaki

PVP 2006; 113-121doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93220

Abstract

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Topics: Cycles , Fatigue , Fatigue damage , Fatigue life , Fatigue testing , Pressurized water reactors , Stress , Temperature , Transients (Dynamics) , Water

Fatigue Crack Growth Curve for Austenitic Stainless Steels in PWR Environment

Yuichiro Nomura, Katsumi Sakaguchi, Hiroshi Kanasaki, Shigeki Suzuki

PVP 2006; 123-128doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93224

Abstract

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

JSME Codes on Environmental Fatigue Evaluation

Takao Nakamura, Makoto Higuchi, Takehiro Kusunoki, Yasuaki Sugie

PVP 2006; 129-138doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93305

Abstract

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Topics: Fatigue , JSME Standards , Japan Society of Mechanical Engineers , Evaluation methods , Fatigue life , Light water reactors , Public utilities , Concretes , Natural resources , Nuclear engineering

Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water

John Hickling, Renate Kilian, Leslie Spain, John Carey

PVP 2006; 139-151doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93318

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Topics: Fatigue testing , Pressurized water reactors , Stainless steel , Water , Flow (Dynamics) , Fatigue , Fracture (Materials) , Carbon steel , Corrosion , Cycles

Crack Growth Rates of Nickel Alloy Welds in a PWR Environment

Bogdan Alexandreanu, Omesh K. Chopra, William J. Shack

PVP 2006; 153-162doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93594

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Topics: Fracture (Materials) , Nickel alloys , Pressurized water reactors , Welded joints , Alloys , Metals , Cracking (Materials) , Fatigue , Fracture (Process) , Coolants

Fatigue of Stabilized SS and 316 NG Alloy in PWR Environment

Jussi P. Solin

PVP 2006; 163-173doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93833

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Topics: Alloys , Fatigue , Pressurized water reactors , Steel , Fatigue testing , Oxygen , Stainless steel , Titanium , Water

A Review of Fatigue and SCC Crack Growth Rate Relationships for Ferritic and Stainless Steels and Ni-Cr-Fe Materials in BWR Environment

Hardayal S. Mehta

PVP 2006; 175-190doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93853

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Topics: Boiling water reactors , Fatigue , Fracture (Materials) , Stainless steel , Corrosion , Fatigue cracks , Water , Alloy steel , Cracking (Materials) , Fracture (Process)

The Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials

Omesh K. Chopra, William J. Shack

PVP 2006; 191-204doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93889

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Topics: Coolants , Fatigue life , Light water reactors , Fatigue , Steel , Heat , Alloy steel , ASME Standards , Carbon , Finishes

Application of Environmental Fatigue Penalty Factors and Implications for Design Analyses

Mark A. Gray, E. Lyles Cranford, III, Paul R. Donavin

PVP 2006; 205-212doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93982

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Topics: Design , Fatigue , Transients (Dynamics) , ASME Standards , Fatigue design , Licensing , Stainless steel , Stress , Water

Fatigue and Ratcheting in Pressure Vessel Design

Design Fatigue Life Comparison of ASME Section VIII and EN 13445 Vessels With Welded Joints

Arturs Kalnins, Mahendra Rana, Guido G. Karcher

PVP 2006; 215-223doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93059

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Topics: Design , Fatigue life , Vessels , Welded joints , ASME Standards , Cycles , ASME Boiler and Pressure Vessel Code , Fatigue strength , Stress

A Discussion on the Performance of Continuum Plasticity Models for Fatigue Lifetime Assessment Based on the Local Strain Appraoch

Abi´lio M. P. De Jesus, He´lder F. S. G. Pereira, Alfredo S. Ribeiro, Anto´nio A. Fernandes

PVP 2006; 225-235doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93460

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Topics: Fatigue , Plasticity , Stress , Hardening , Cycles , Fatigue life , Kinematics , Nozzles , Steel , Finite element analysis

Low-Cycle Fatigue Evaluation Using the Weld Master S-N Curve

P. Dong, Z. Cao, J. K. Hong

PVP 2006; 237-246doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93607

Abstract

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Topics: Approximation , Cycles , Fatigue , Low cycle fatigue , Pipes , Stress , Stress-strain curves , Vessels , Welded joints

Comparison of Fatigue Damage Estimates Using the ASME Code and Other Methods

Som Chattopadhyay

PVP 2006; 247-254doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93646

Abstract

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Topics: ASME Standards , Fatigue damage , Fatigue , Stress , Design , Finite element analysis , Low cycle fatigue , Cycles , Safety , Stress analysis (Engineering)

Development of New S-N Curves Based on Small Crack Methodology

Som Chattopadhyay, Juan Hu

PVP 2006; 255-261doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93778

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Topics: Fracture (Materials) , Fatigue cracks , Fatigue design , Fracture mechanics , Plasticity , Pressure vessels , Stress

Evaluation of Alternate Interpretations Regarding the Conditions for Exclusion of Thermal Bending Stresses in Simplified Elastic-Plastic Stress Analyses

Robert B. Keating, Richard O. Vollmer

PVP 2006; 263-268doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93788

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Topics: Bending (Stress) , Stress analysis (Engineering) , Stress , ASME Standards , Fatigue , Finite element analysis , Geometry , Temperature distribution

Creep-Fatigue Life Assessment Under Multiaxial Strain State

Shengde Zhang, Masao Sakane, Takamoto Itoh

PVP 2006; 269-275doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93807

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Topics: Creep , Fatigue , Damage , Waves , Compression , Density , Finite element analysis , Gages , Stainless steel , Stress

Universal J-Integral to Assess Multiaxial Low Cycle Fatigue

Takamoto Itoh, Masao Sakane, Dimitar Tchankov, Naomi Hamada

PVP 2006; 277-284doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93810

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Topics: Low cycle fatigue , Fracture (Materials) , Displacement , Crack propagation , Electromagnetic scattering , Geometry , Nickel , Solders , Stainless steel , Steel

Fatigue Testing and Life Estimates of Welded Flat Head Pressure Vessel Joints

Chris Hinnant

PVP 2006; 285-297doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93967

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Topics: Fatigue testing , Pressure vessels , Fatigue , Cycles , Fatigue design , Shells , Stainless steel , Welded joints , American Petroleum Institute , Carbon steel

A Critical Analysis of the Plasticity Correction Factors Proposed in the EN13445 Standard for Fatigue Analysis of Unwelded Material

He´lder F. S. G. Pereira, Abi´lio M. P. De Jesus, Alfredo S. Ribeiro, Anto´nio A. Fernandes

PVP 2006; 299-308doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94030

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Topics: Fatigue analysis , Plasticity , Stress , Fatigue , Yield stress

Fatigue Design Check of Welded Regions: A Proposal for Combining EN 13445 and ASME Division VIII Section 2 Rewrite Concepts

Josef L. Zeman

PVP 2006; 309-316doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94031

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Topics: Fatigue design , Engineering standards , Joining

Interaction and Combination of Multiple Flaws

Alignment Rules for Non-Aligned Flaws at LEFM Evaluation Procedures

Kunio Hasegawa, Koichi Saito, Katsumasa Miyazaki

PVP 2006; 319-324doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93047

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Topics: Brittle fracture , Carbon steel , Finite element methods , Finite element model , Fracture (Materials) , Fracture (Process) , Plates (structures) , Stress

Flaw Proximity Rules for Parallel Surface Cracks Based on Elastic, Elastic-Plastic Fracture Mechanics and Limit Load Analyses

Masayuki Kamaya

PVP 2006; 325-332doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93341

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Topics: Fracture mechanics , Stress , Surface cracks , Fracture (Materials) , ASME Boiler and Pressure Vessel Code , Finite element methods , Fracture toughness , Reliability

Interaction of Twin Non-Aligned Through-Wall Flaws Under Elastic-Plastic Conditions

B. Bezensek, E. McCulloch

PVP 2006; 333-340doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93373

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Topics: Fracture (Materials) , Geometry , Separation (Technology) , Shear flow , Stress , Tension

New and Recent Revised Japanese Codes and Standards

Fracture Toughness of Highly Irradiated Pressure Vessel Steels in the Upper Shelf Temperature

Hiroshi Matsuzawa, Toru Osaki

PVP 2006; 343-353doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93032

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Topics: Fracture toughness , Pressure vessels , Steel , Temperature , Fluence (Radiation measurement) , Reactor vessels , Neutrons , Concretes , Neutron flux , Nuclear power stations

Fracture Behavior of Thermally Aged Primary Coolant Piping Made of Cast Stainless Steel

Hiroshi Matsuzawa, Toru Osaki

PVP 2006; 355-361doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93033

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Topics: Coolants , Fracture (Materials) , Pipes , Stainless steel , Tensile strength , Crack detection , Fracture toughness , Reactor vessels , Light water reactors , Nuclear power stations

2004 Edition of Japanese Fitness-for-Service Code for Nuclear Power Plants

Koichi Kashima, Tomonori Nomura, Koji Koyama

PVP 2006; 363-369doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93190

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

Plastic Collapse Assessment Procedure for Vessel With Local Thin Area Simultaneously Subjected to Internal Pressure and External Bending Moment

Shinji Konosu, Norihiko Mukaimachi

PVP 2006; 371-385doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93496

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Topics: Collapse , Pressure , Vessels , Cylinders , Compression , Earthquakes , Finite element analysis , Pipes , Pressure equipment , Storage tanks

Failure Assessment Curves (FACs) in Japanese FFS Code, HPIS Z101 Level 2

Shinji Konosu

PVP 2006; 387-398doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93498

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Topics: Failure , Fitness-for-service , Steel , Carbon steel , American Petroleum Institute , Fracture (Materials) , Fracture mechanics , High pressure (Physics) , Plasticity , Yield point

Partial Safety Factor (PSF) Approach in Japanese FFS Code, HPIS Z101 Level 2

Ikuo Kojima, Shinji Konosu

PVP 2006; 399-406doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93528

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Topics: Fitness-for-service , Safety , Fracture (Materials) , American Petroleum Institute , Dimensions , Materials properties , Pressure equipment , Stress

New Code Case to Substitute the Allowable Crack Angle in Rules on Fitness-for-Service

Hideo Machida, Koichi Kashima

PVP 2006; 407-414doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93542

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Topics: Fitness-for-service , Fracture (Materials) , Japan Society of Mechanical Engineers , Maintenance , Pipes , Stability , Surface cracks , Overlays (Materials engineering)

A Rational Identification of Creep Design Area Using Negligible Creep Curves

Masayuki Sukekawa, Nobuhiro Isobe, Hiroshi Shibamoto, Yoshihiko Tanaka, Naoto Kasahara

PVP 2006; 415-419doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93544

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Topics: Creep , Design , Stress , Fast neutron reactors , Steel , Temperature , Ferrites (Magnetic materials) , High temperature , Materials properties , Relaxation (Physics)

Guideline of Weld Overlay Repair Method for Primary Piping of Japanese Boiling Water Reactors

Haruo Fujimori, Eisaku Hayashi, Yuichi Motora, Hitoshi Ohata, Hideo Sakurai

PVP 2006; 421-427doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93690

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Topics: Boiling water reactors , Maintenance , Overlays (Materials engineering) , Pipes

Open Inspection Intervals of Boilers and Pressure Vessels for Chemical Plants in Japan

Kotoji Ando, Kazuharu Kitano

PVP 2006; 429-433doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93712

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Topics: Boilers , Inspection , Pressure vessels

Study on Reliability of Nuclear Power Plant Piping Considering Defect Sizing Accuracy

Hideo Machida

PVP 2006; 435-442doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93775

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Topics: Nuclear power stations , Pipes , Reliability , Fitness-for-service , Fracture (Materials) , Probability , Boiling water reactors , Failure , Safety , Stability

Overview of the Japanese Code of Surveillance Test Program for Reactor Vessels

Minoru Tomimatsu, Seiji Asada, Hitoshi Ohata, Hideo Kobayashi

PVP 2006; 443-450doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93785

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Topics: Reactor vessels , Surveillance , Nuclear reactors , Design , Energy engineering , Inspection , Mechanical properties , Radiation (Physics) , Temperature , Vessels

Overview of the JEA Code of Fracture Toughness Requirements for Nuclear Power Plant Components

Minoru Tomimatsu, Seiji Asada, Takashi Hirano, Hideo Kobayashi

PVP 2006; 451-457doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93786

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Topics: Fracture toughness , Nuclear power stations , Reactor vessels , Temperature , Acceptance criteria , Energy engineering , Evaluation methods , Inspection , Pressure , Thermal shock

Residual Stress Assessment in Japanese FFS Code for Pressure Equipment, HPIS Z101

Yoshio Takagi, Shinji Konosu, Masataka Yatomi

PVP 2006; 459-465doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93808

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Topics: Fitness-for-service , Pressure equipment , Stress

New Developments in Codes and Standards

Computer Based Process Piping Stress Analysis: ASME B31.3 Appendix S — Example S1

Don R. Edwards

PVP 2006; 469-477doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93036

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Topics: Computers , Process piping , Stress analysis (Engineering) , Design , Pressure , Temperature , Pipes , Ambiguity , Computer software , Fluids

Comparison of Pressure Vessel Codes ASME Section VIII and EN13445

Leslie P. Antalffy, J. J. Hajovsky, George A. Miller, III, Barry J. Millet, Jeffrey A. Pfeifer, George T. West

PVP 2006; 479-488doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94010

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Topics: Pressure vessels , Design , ASME Boiler and Pressure Vessel Code , Manufacturing , Materials properties , Mechanical engineers , Pressure equipment , Vessels

Computer Based Process Piping Stress Analysis: ASME B31.3 Appendix S — Example S2

Don R. Edwards

PVP 2006; 489-497doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94023

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Topics: Computers , Process piping , Stress analysis (Engineering) , Stress , Pipes , Displacement , Operating temperature , Computer software , Fluids , Petroleum refinery piping

European Pressure Vessel Standards: Further Progress

Ed Haynes

PVP 2006; 499-506doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94035

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Topics: Pressure vessels , Design , Pressure equipment , Aluminum , Cast iron , Creep , Engineering design processes , Engineering standards , Joining , Nondestructive evaluation

Safe Operation and FFS Assessment for Pressure Equipment: Updated With Study for Local Metal Loss Assessment

Atsushi Ohno, Yoshiaki Uno, Takayasu Tahara

PVP 2006; 507-514doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94040

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Topics: Fitness-for-service , Inspection , Metals , Pressure equipment

Structural Integrity of Pressure Components

Determination of MAWP of a Slab Tank Using FEA

Yogeshwar Hari

PVP 2006; 517-522doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93176

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Topics: Finite element analysis , Slabs , Pressure , Stress , ASME Standards , Computer software , Deflection , Design

Reconsideration of the Allowable Local Thickness of Straight Pipes in ASME CC N-597

Jai Hak Park, Kyu In Shin, Chi Yong Park, Sung Ho Lee, Tae Ryong Kim

PVP 2006; 523-530doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93493

Abstract

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Topics: Pipes , Bending (Stress) , Finite element methods , Stress , Stress analysis (Engineering)

Design and Manufacturing of VVER-1500 Reactor Vessel Principal Problems and Ways of Their Solution

V. I. Bakaldin, V. I. Kashirin, V. V. Petrov, V. G. Fedosov, G. V. Fedosova

PVP 2006; 531-539doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94032

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Topics: Design , Manufacturing , Reactor vessels , Construction , Dimensions , Mechanical properties , Shells , Vessels , Epoxy resins , Manufacturing technology

Application of Risk-Based Inspection in Safety Assessment of Pressure Equipment of Chinese Petrochemical Plants

Xuedong Chen, Tiecheng Yang, Bing Wang, Zhibin Ai, Chuanqing Cheng

PVP 2006; 541-549doi:https://doi.org/10.1115/PVP2006-ICPVT-11-94044

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Topics: Petrochemicals , Pressure equipment , Risk-based inspection , Safety

Tube Integrity of Steam Generators in Nuclear Service

Probability of Burst in Steam Generator Tubes Using Monte Carlo Method

Jae Bong Lee, Jai Hak Park, Hong-Deok Kim, Han-Sub Chung, Tae Ryong Kim

PVP 2006; 553-561doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93469

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Topics: Boilers , Monte Carlo methods , Probability , Nondestructive evaluation , In-service inspection , Cycles , Engineering simulation , Simulation

Fitness-for-Service Assessment for Steam Generator Tube Fretting at Darlington Nuclear Generating Station

Sandra Pagan, Brian E. Mills, Michael J. Kozluk

PVP 2006; 563-572doi:https://doi.org/10.1115/PVP2006-ICPVT-11-93787

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Topics: Boilers , Fitness-for-service , Power stations , Maintenance , Energy generation , Feedback , Industrial research , Inspection , Leakage , Life cycle management