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

Topics: Carbon steel , Stress , Welded joints , Hydrogen , Cracking (Materials) , Fracture (Materials) , Fracture (Process) , Pipes , American Petroleum Institute , Methane

New Fatigue Screening Criteria for the Fitness-for-Service Assessment of In-Service Process Piping Vibrations

Michael F. P. Bifano, Lyle Breaux, Anthony J. Feller, Richard Brodzinski

PVP 2018; V01AT01A002doi:https://doi.org/10.1115/PVP2018-84847

Abstract

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Topics: Fatigue , Fitness-for-service , Process piping , Vibration , Pipes , American Petroleum Institute , Finite element analysis , Stress , Cycles , Downtime

A Residual Stress Profile Estimation Method for Narrow Groove Girth Welds

Shaopin Song, Pingsha Dong

PVP 2018; V01AT01A003doi:https://doi.org/10.1115/PVP2018-84858

Abstract

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Topics: Stress , Welded joints , Wall thickness , American Petroleum Institute , Density , Finite element analysis , Fitness-for-service , Heat , Heating , Membranes

A Comprehensive Structural Strain Method Incorporating Strain-Hardening Effects: From LCF to Ratcheting Evaluations

Xianjun Pei, Pingsha Dong, Shaopin Song, David Osage

PVP 2018; V01AT01A004doi:https://doi.org/10.1115/PVP2018-84860

Abstract

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Topics: Algorithms , Aluminum , Cycles , Fatigue analysis , Fatigue life , Low cycle fatigue , Pipes , Plane strain , Steel , Stress

ASME Section XI Code Activities

Stress Intensity Factor Coefficients for Circumferential OD Surface Flaws in Cylinders for Appendix A of ASME Section XI

Darrell R. Lee, Russell C. Cipolla, Michael C. Liu

PVP 2018; V01AT01A005doi:https://doi.org/10.1115/PVP2018-84381

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Topics: Cylinders , Stress , American Petroleum Institute , ASME Boiler and Pressure Vessel Code , Fittings , Fracture (Materials) , Fracture mechanics , Interpolation , Polynomials , Surface cracks

Fatigue Crack Growth in Low Alloy Steels Under Tension-Compression Loading in Air

Kisaburo Azuma, Yasuhiro Yamazaki

PVP 2018; V01AT01A006doi:https://doi.org/10.1115/PVP2018-84467

Abstract

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Topics: Alloy steel , Compression , Fatigue cracks , Tension , Fracture (Materials) , Stress , ASME Boiler and Pressure Vessel Code , ASME Standards , Cycles , Nuclear power stations

Three Approaches to Quantification of NDE Uncertainty and a Detailed Exposition of the Expert Panel Approach Using the Sheffield Elicitation Framework

Jeffrey T. Fong, N. Alan Heckert, James J. Filliben, Steven R. Doctor

PVP 2018; V01AT01A007doi:https://doi.org/10.1115/PVP2018-84771

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Topics: Nondestructive evaluation , Uncertainty , Fracture (Materials) , Inspection , Experimental design , Pressure vessels , Probes , Risk , Steel , Boilers

Limit Load Solution of Non-Aligned Multiple Flaws

Fuminori Iwamatsu, Katsumasa Miyazaki, Koichi Saito

PVP 2018; V01AT01A008doi:https://doi.org/10.1115/PVP2018-84809

Abstract

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Topics: Stress , Collapse , Finite element analysis , Fracture (Materials) , Fracture (Process) , Power stations , Boilers , Evaluation methods , Experimental methods , Fitness-for-service

Definition of Fatigue Crack Growth Thresholds for Ferritic Steels in Fitness-for-Service Codes

Kunio Hasegawa, Bohumir Strnadel

PVP 2018; V01AT01A009doi:https://doi.org/10.1115/PVP2018-84940

Abstract

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Topics: Fatigue cracks , Fitness-for-service , Steel , Stress , ASME Standards , Fatigue testing , Fracture (Materials) , Structural elements (Construction)

Fatigue Crack Growth for Ferritic Steel Under Negative Stress Ratio

Yoshihito Yamaguchi, Kunio Hasegawa, Yinsheng Li

PVP 2018; V01AT01A010doi:https://doi.org/10.1115/PVP2018-84961

Abstract

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Topics: Fatigue cracks , Steel , Stress , Fracture (Materials) , ASME Standards , Cycles , Fatigue testing , High temperature

Revision to Stress Intensity Factor Equations for ASME Section XI Appendix C-4000: Determination of Failure Mode

Kiminobu Hojo, Steven Xu

PVP 2018; V01AT01A011doi:https://doi.org/10.1115/PVP2018-85051

Abstract

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Topics: Failure mechanisms , Stress , Pipes , Bending (Stress) , Dimensions , Materials properties , Membranes , Shapes , Temperature

Investigation of Calculating Stress Intensity Factor at Surface Point and its Inclusion in Engineering Standards

Steven X. Xu, Greg Thorwald, Patrick Le Delliou, Russell C. Cipolla

PVP 2018; V01AT01A012doi:https://doi.org/10.1115/PVP2018-85093

Abstract

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Topics: Engineering standards , Stress , Cylinders , Fittings , Errors , Fracture mechanics

Environmental Fatigue Issues

INCEFA-PLUS: Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment

Kevin Mottershead, Matthias Bruchhausen, Sam Cuvilliez, Sergio Cicero

PVP 2018; V01AT01A013doi:https://doi.org/10.1115/PVP2018-84034

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Topics: Fatigue , Nuclear power stations , Safety , Finishes , Stress , Testing , Databases , Fatigue damage , Light water reactors , Stainless steel

Ensuring Data Quality for Environmental Fatigue: INCEFA-PLUS Testing Procedure and Data Evaluation

Marc Vankeerberghen, Matthias Bruchhausen, Román Cicero, Luc Doremus, Jean-Christophe Le-Roux, Norman Platts, Philippe Spätig, Marius Twite, Kevin Mottershead

PVP 2018; V01AT01A014doi:https://doi.org/10.1115/PVP2018-84081

Abstract

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Topics: Fatigue , Testing , Fatigue testing , Light water reactors , Nuclear power stations , Databases , Fatigue life , Finishes , Nuclear industry , Safety

Low Cycle Fatigue (EAF) of AISI 304L and 347 in PWR Water

Tommi Seppänen, Jouni Alhainen, Esko Arilahti, Jussi Solin

PVP 2018; V01AT01A015doi:https://doi.org/10.1115/PVP2018-84197

Abstract

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Topics: Electric arc furnaces , Low cycle fatigue , Pressurized water reactors , Water , Stainless steel , Accounting , ASME Standards , ASTM standards , Design , Fatigue

Explicit Quantification of the Interaction Between the PWR Environment and Component Surface Finish in Environmental Fatigue Evaluation Methods for Austenitic Stainless Steels

Thomas Métais, Andrew Morley, Laurent de Baglion, David Tice, Gary L. Stevens, Sam Cuvilliez

PVP 2018; V01AT01A016doi:https://doi.org/10.1115/PVP2018-84240

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Topics: Evaluation methods , Fatigue , Finishes , Pressurized water reactors , Stainless steel , Nuclear power stations , Testing , Fatigue life , Design , Polishing

Effect of Surface Condition on the Fatigue Life of Austenitic Stainless Steels in High Temperature Water Environments

Andrew Morley, Marius Twite, Norman Platts, Alec McLennan, Chris Currie

PVP 2018; V01AT01A017doi:https://doi.org/10.1115/PVP2018-84251

Abstract

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Topics: Fatigue life , High temperature , Stainless steel , Water , Design , Fatigue design , Finishes , Surface roughness , Accounting , Alloys

Negative R Fatigue Crack Growth Rate Testing on Austenitic Stainless Steel in Air and Simulated Primary Water Environments

Norman Platts, Ben Coult, Wenzhong Zhang, Peter Gill

PVP 2018; V01AT01A018doi:https://doi.org/10.1115/PVP2018-84252

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Topics: Fatigue cracks , Stainless steel , Testing , Water , Stress , Fracture (Materials) , High temperature , Tension , Coolants , Corners (Structural elements)

Environmental Assisted Fatigue and EDF 900 MWe PWRs Fleet: Towards an Exemption of Environmental Effects Consideration for Secondary Circuit Components

Sam Cuvilliez, Gaëlle Léopold, Thomas Métais

PVP 2018; V01AT01A019doi:https://doi.org/10.1115/PVP2018-84301

Abstract

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Topics: Circuits , Fatigue , Pressurized water reactors , Electric arc furnaces , Fatigue testing , Nuclear power stations , Alloys , Coolants , Design , Inspection

ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)

Anees Udyawar, Charles Tomes, Alexandria Carolan, Steve Marlette, Thomas Meikle, Warren Bamford

PVP 2018; V01AT01A020doi:https://doi.org/10.1115/PVP2018-84346

Abstract

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Topics: Licensing , Piping systems , Pressurized water reactors , Fatigue , Transients (Dynamics) , Cycles , In-service inspection , Inspection , Construction , Design

Influence of Mean Strain on Fatigue Life of Stainless Steel in PWR Water Environment

Masayuki Kamaya

PVP 2018; V01AT01A021doi:https://doi.org/10.1115/PVP2018-84461

Abstract

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Topics: Fatigue life , Pressurized water reactors , Stainless steel , Water , Work hardening , Japan Society of Mechanical Engineers , Low temperature , Stress , Surface roughness , Deformation

Study on the Influence of Strain Rate on Crack Initiation and Growth in Simulated Reactor Coolant Environment of Type 316 Stainless Steel

Takahisa Nose, Takao Nakamura, Takanori Kitada

PVP 2018; V01AT01A022doi:https://doi.org/10.1115/PVP2018-84490

Abstract

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Topics: Fracture (Materials) , Nuclear reactor coolants , Stainless steel , Crack propagation , Fatigue , Fatigue cracks , Fatigue damage , Fatigue life , Fatigue testing , Maintenance

Creep-Fatigue Damage Evaluation of Grade 91 Steel Using Interrupt Creep Fatigue Test

Uijeong Ro, Jeong Hwan Kim, Hoomin Lee, Seok Jun Kang, Moon Ki Kim

PVP 2018; V01AT01A023doi:https://doi.org/10.1115/PVP2018-84561

Abstract

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Topics: Creep , Damage , Fatigue , Fatigue testing , Steel , Testing , Nuclear power stations , Finite element model , Operating temperature , Pipes

Standards-Based Technologies for Exchanging Fatigue Test Data

Tim Austin, Lianshan Lin, Thomas Métais

PVP 2018; V01AT01A024doi:https://doi.org/10.1115/PVP2018-84610

Abstract

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Topics: Fatigue testing , Workshops (Work spaces) , Aerospace industry , Design , Energy generation , Engineering systems and industry applications , Errors , Fatigue , Nuclear power stations , Safety

Nuclear Fatigue Codified Design Rules: Development Status, Margins and Screening Criteria

Claude Faidy

PVP 2018; V01AT01A025doi:https://doi.org/10.1115/PVP2018-84698

Abstract

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Topics: Design , Fatigue , Fatigue design , Fatigue life , ASME Boiler and Pressure Vessel Code , Coolants , Engineering standards , Fatigue testing , Light water reactors , Roads

Further Validation of the Strain-Life Weighted (SNW) F_en Method for Plant Realistic Strain and Temperature Waveforms

Chris Currie, Andrew Morley, Daniel Leary, Norman Platts, Marius Twite, Keith Wright

PVP 2018; V01AT01A026doi:https://doi.org/10.1115/PVP2018-84879

Abstract

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Topics: Temperature , Fatigue , Cycles , Pressurized water reactors , Water , Accounting , Coolants , Fatigue life , Nuclear power stations , Oxygen

A Thermomechanical PWR Test Facility to Investigate Thermal Shock Loading on a Small Scale Tubular Specimen

Peter Gill, Norman Platts, Chris Currie, Eleanor Grieveson

PVP 2018; V01AT01A027doi:https://doi.org/10.1115/PVP2018-84923

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Topics: Pressurized water reactors , Test facilities , Thermal shock , Thermomechanics , Geometry , Stress analysis (Engineering) , Finite element analysis , Flow (Dynamics) , Heat transfer coefficients , Temperature

Cyclic, Monotonic and Fatigue Performance of Stabilized Stainless Steel in PWR Water and Research Laboratory

Jussi Solin, Jouni Alhainen, Tommi Seppänen, H. Ertugrul Karabaki, Wolfgang Mayinger

PVP 2018; V01AT01A028doi:https://doi.org/10.1115/PVP2018-84935

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Topics: Fatigue , Pressurized water reactors , Stainless steel , Water , Cycles , Endurance limit , Nuclear power stations , Temperature , Ductility , Fatigue life

Hidden Roles of Time and Temperature in Cyclic Behavior of Stainless Nuclear Piping

Jussi Solin, Tommi Seppänen, Wolfgang Mayinger, H. Ertugrul Karabaki

PVP 2018; V01AT01A029doi:https://doi.org/10.1115/PVP2018-84936

Abstract

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Topics: Pipes , Temperature , Design , Fatigue , Pressurized water reactors , Stainless steel , Water , ASME Standards , Databases , Doors

Fatigue and Ratcheting Issues in Pressure Vessel and Piping Design

Application of the Enhanced Reference Stress Method to Fatigue Propagation of a Surface Crack in a Plate Subjected to Cyclic Bending

Ippei Yamasaki, Terutaka Fujioka, Yasuhiro Shindo, Yusuke Kaneko

PVP 2018; V01AT01A030doi:https://doi.org/10.1115/PVP2018-84233

Abstract

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Topics: Fatigue , Stress , Surface cracks , Finite element analysis , Crack propagation , Computers , Fatigue cracks , Fracture (Materials) , Fracture mechanics , Geometry

An Effect of Nozzle Flexibilities/Stiffness on Equipment Nozzle Loads and Local Stresses

Sujay S. Pathre, K. Govindan

PVP 2018; V01AT01A031doi:https://doi.org/10.1115/PVP2018-84952

Abstract

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Topics: Nozzles , Stiffness , Stress , Engineers , Pipes , Junctions , Closed loop systems , Finite element methods , Pressure vessels , Shells

Beyond Shakedown-Ratcheting Boundary

R. Adibi-Asl, W. Reinhardt

PVP 2018; V01AT01A032doi:https://doi.org/10.1115/PVP2018-85050

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , Damage , Deformation , Design , Fatigue , Fatigue damage , Finite element analysis , Pipes , Pressure vessels , Stress

Fatigue Monitoring and Related Assessment Methods

Fatigue Monitoring: Case Studies in Nuclear Power Plant

G. Bourguigne, F. Schroeter

PVP 2018; V01AT01A033doi:https://doi.org/10.1115/PVP2018-84007

Abstract

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Topics: Fatigue , Nuclear power stations , Cycles , Design , Fatigue damage , Life extension , Monitoring systems , Thermal stratification , Transients (Dynamics)

Fatigue Monitoring of a Dented Piping Specimen Using Infrared Thermography

Vitor Eboli L. Paiva, G. L. G. Gonzáles, R. D. Vieira, J. E. Maneschy, R. B. Vieira, J. L. F. Freire

PVP 2018; V01AT01A034doi:https://doi.org/10.1115/PVP2018-84597

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Topics: Fatigue , Pipes , Thermography , Damage , Fatigue damage , Fatigue properties , Hydrostatic pressure , Inspection , Locks (Waterways) , Nondestructive evaluation

Issues With Multiaxial Fatigue Assessment in the ASME Boiler and Pressure Vessel Code

Marco Antonio Meggiolaro, Jaime Tupiassú Pinho de Castro, Hao Wu

PVP 2018; V01AT01A035doi:https://doi.org/10.1115/PVP2018-84979

Abstract

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Topics: ASME Boiler and Pressure Vessel Code , Fatigue , Stress , Fatigue cracks , Fatigue damage , Torsion

Hydrogen Effects on Material Behavior for Structural Integrity Assessment

Introduction of Technical Document in Japan for Safe Use of Ground Storage Vessels Made of Low Alloy Steels for Hydrogen Refueling Stations

Hajime Fukumoto, Yoru Wada, Hisao Matsunaga, Takeru Sano, Hiroshi Kobayashi

PVP 2018; V01AT01A036doi:https://doi.org/10.1115/PVP2018-84099

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Topics: Alloy steel , Hydrogen , Storage , Vessels , Fatigue cracks , Tensile strength , Fatigue testing , High-pressure vessels , Hydrogen embrittlement , Inspection

Effect of Pre-Heat Treatment on Hydrogen Concentration Behavior of y-Grooved Weld Joint Based on a Coupled Analysis of Heat Transfer-Thermal Stress-Hydrogen Diffusion

Go Ozeki, A. Toshimitsu Yokobori, Jr., Toshihito Ohmi, Tadashi Kasuya, Nobuyuki Ishikawa, Satoshi Minamoto, Manabu Enoki

PVP 2018; V01AT01A037doi:https://doi.org/10.1115/PVP2018-84178

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Topics: Diffusion (Physics) , Heat , Hydrogen , Stress , Thermal stresses , Cooling , Heat transfer , Temperature , Cracking (Materials) , Finite element methods

Hydrogen Diffusion Concentration Behaviors for Square Groove Weld Joint

Toshihito Ohmi, A. Toshimitsu Yokobori, Jr., Go Ozeki, Tadashi Kasuya, Nobuyuki Ishikawa, Satoshi Minamoto, Manabu Enoki

PVP 2018; V01AT01A038doi:https://doi.org/10.1115/PVP2018-84192

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Topics: Diffusion (Physics) , Hydrogen , Thermal stresses , Cooling , Cracking (Materials) , Fracture (Process) , Heat transfer , Heat , Hydrogen embrittlement , Metals

Effect of Hydrogen on Fracture Toughness Behavior of 2.25Cr-1Mo-0.25V Steel

Mengyu Chai, Yan Song, Zaoxiao Zhang, Quan Duan, Guangxu Cheng

PVP 2018; V01AT01A039doi:https://doi.org/10.1115/PVP2018-84486

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Topics: Fracture toughness , Hydrogen , Steel , Fracture (Materials) , Alloys , ASTM International , Brittle fracture , Damage , Ductility , Fracture mechanics

A Compendium of Mechanical Testing of Austenitic Stainless Steels in Hydrogen

Poh-Sang Lam, Andrew J. Duncan, Michael J. Morgan, Robert L. Sindelar, Thad M. Adams

PVP 2018; V01AT01A040doi:https://doi.org/10.1115/PVP2018-84723

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Topics: Hydrogen , Mechanical testing , Stainless steel , Ductility , Grain size , Nickel , Rivers , High pressure (Physics) , Alloys , Elongation

Hydrogen Compatibility and Suitability of (Ni)-Cr-Mo High-Strength Low-Alloy Seamless Line Pipe Steels for Pressure Vessels for Hydrogen Storage

Akihide Nagao, Nobuyuki Ishikawa, Toshio Takano

PVP 2018; V01AT01A041doi:https://doi.org/10.1115/PVP2018-84726

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Topics: Alloys , Hydrogen , Hydrogen storage , Pipes , Pressure vessels , Steel , High pressure (Physics) , Mechanical properties , Storage , Elongation

Cycle-Wise Process-Zone Model for Prediction of Delayed Hydride Cracking Initiation Under Flaw-Tip Hydride Ratcheting Conditions

Steven X. Xu, Jun Cui, Douglas A. Scarth, David Cho

PVP 2018; V01AT01A042doi:https://doi.org/10.1115/PVP2018-85116

Abstract

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Topics: Cracking (Materials) , Cycles , Fracture (Process) , Heat , Fuels , Pressure , Stress , Bearings , Corrosion , Creep

Hydrogen Flakes Assessment in the RPVs

Mechanical Behaviour of a Forged Ferritic Steel Shell Containing Numerous Hydrogen Flakes

C. Jacquemoud, I. Delvallée-Nunio

PVP 2018; V01AT01A043doi:https://doi.org/10.1115/PVP2018-84087

Abstract

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Topics: Hydrogen , Mechanical behavior , Shells , Steel , Boilers , Engineering simulation , Finite element methods , Finite element model , Forgings (Products) , Safety

Experimental and Numerical Investigations on the Failure Behavior of Pressurized Components Containing Crack Fields

Patrick Gauder, Xaver Schuler, Michael Seidenfuss

PVP 2018; V01AT01A044doi:https://doi.org/10.1115/PVP2018-84155

Abstract

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Topics: Failure , Fracture (Materials) , Shear (Mechanics) , Hydrogen , Computer simulation , Damage , Damage mechanics , Nuclear power stations , Steel , Stress

Towards a Process for the Assessment of Mixed Mode I+II Fracture Toughness

Afaf Bouydo, Valéry Lacroix, Rachid Chaouadi, Vratislav Mares

PVP 2018; V01AT01A045doi:https://doi.org/10.1115/PVP2018-84575

Abstract

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Topics: Fracture toughness , Fracture (Materials) , Fitness-for-service , Geometry , Engineering simulation , Fracture mechanics , Hydrogen , Pressure vessels , Simulation , Steel

Numerical Investigations on the Interaction of Cracks in Quasi-Laminar Crack Fields

Christian Swacek, Xaver Schuler, Michael Seidenfuss

PVP 2018; V01AT01A046doi:https://doi.org/10.1115/PVP2018-84688

Abstract

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Topics: Fracture (Materials) , Damage , Hydrogen , Finite element analysis , Mechanical behavior , Nondestructive evaluation , Nuclear power stations , Pressure , Pressure vessels , Reactor vessels

Improvement of Flaw Characterization Rules in Fitness-for-Service Codes

Plastic Collapse Stresses for Pipes With Circumferential Twin Flaws Using Combination Rules

Kunio Hasegawa, Yinsheng Li, Yun-Jae Kim, Valery Lacroix, Bohumir Strnadel

PVP 2018; V01AT01A047doi:https://doi.org/10.1115/PVP2018-84019

Abstract

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Topics: Collapse , Pipes , Stress , Fitness-for-service , Bending (Stress) , Japan Society of Mechanical Engineers , Stainless steel

Rules for Flaw Interaction for Subsurface Flaws in Operating Pressurized Vessels: Technical Basis of Code Case N-877

Valéry Lacroix, Pierre Dulieu, Sebastien Blasset, Ralf Tiete, Yinsheng Li, Kunio Hasegawa, Warren Bamford, Anees Udyawar

PVP 2018; V01AT01A048doi:https://doi.org/10.1115/PVP2018-84120

Abstract

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Topics: ASME Standards , Finite element methods , Finite element model , Fitness-for-service , Inspection , Pressure , Pressure vessels , Sensitivity analysis , Vessels

RSE-M - ASME XI - API 579: Comparison of Failure Assessment Diagrams (FAD)

Claude Faidy

PVP 2018; V01AT01A049doi:https://doi.org/10.1115/PVP2018-84703

Abstract

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Topics: American Petroleum Institute , Failure , Stress , Fracture (Materials) , Fracture toughness

Proposal of New Combination Criterion for Pipe With Circumferential Multiple Cracks Based on Ductile Failure Simulation

Myeong-Woo Lee, Kunio Hasegawa, Yun-Jae Kim

PVP 2018; V01AT01A050doi:https://doi.org/10.1115/PVP2018-84822

Abstract

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Topics: Failure , Fracture (Materials) , Pipes , Simulation , Damage , Bending (Stress) , Stress , Collapse , Dimensions , Finite element analysis

Numerical Study on Longitudinal Distance Effect on Failure Stress of Non-Aligned Twin Cracked Pipe

Thanh-Long Nguyen, Myeong-Woo Lee, Kunio Hasegawa, Yun-Jae Kim

PVP 2018; V01AT01A051doi:https://doi.org/10.1115/PVP2018-84838

Abstract

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Topics: Failure , Pipes , Stress , Fracture (Materials) , Damage , Collapse , ASME Standards , Bending (Stress) , Finite element analysis

Prediction for Plastic Collapse Stresses for Pipes With Inner and Outer Circumferential Flaws

Kunio Hasegawa, Yinsheng Li, Vratislav Mares, Valery Lacroix

PVP 2018; V01AT01A052doi:https://doi.org/10.1115/PVP2018-84951

Abstract

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Topics: Collapse , Pipes , Stress , Bending (Stress)

Alternative Characterization Rules for Multiple Surface Planar Flaws

Pierre Dulieu, Valéry Lacroix, Kunio Hasegawa, Yinsheng Li, Bohumir Strnadel

PVP 2018; V01AT01A053doi:https://doi.org/10.1115/PVP2018-84960

Abstract

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Topics: Engineering simulation , Fitness-for-service , Pressure , Simulation

Integrity of Cast Stainless Steel Pipe

Tensile Tests for Cast Stainless Steel: Evolution of the RCC-M Code

Arnaud Blouin, Mathieu Couvrat, Félix Latourte, Julian Soulacroix

PVP 2018; V01AT01A054doi:https://doi.org/10.1115/PVP2018-84601

Abstract

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Topics: Stainless steel , Electromagnetic scattering , Gages , Radiation scattering , Scattering (Physics) , Tensile strength , Mechanical properties , Microscopy , Pressurized water reactors , Temperature

Improvement of Target Flaw Sizes of CASS Pipe for PD Approval Using PFM Code Preface

Wataru Nishi, Takatoshi Hirota, Mayumi Ochi, Daiki Takagoshi, Kiminobu Hojo

PVP 2018; V01AT01A055doi:https://doi.org/10.1115/PVP2018-85015

Abstract

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Topics: Pipes , Ferrites (Magnetic materials) , Collapse , Mechanical properties , Stress , Ductile fracture , Failure mechanisms , Fracture mechanics , Nondestructive evaluation , Sensitivity analysis

Integrity of Reactor Pressure Vessels and Internals for Codes

Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI

Milan Brumovsky

PVP 2018; V01AT01A056doi:https://doi.org/10.1115/PVP2018-84140

Abstract

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Topics: Control systems , Cracking (Materials) , Creep , Design , Dimensions , Embrittlement , Failure , Ferrites (Magnetic materials) , Fracture (Process) , Fracture mechanics

Fracture Analysis of Ductile-Brittle Transition Temperature Region Considering Specimens With Different Constraints

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Kentaro Yoshimoto, Yasuto Nagoshi, Shinichi Kawabata

PVP 2018; V01AT01A057doi:https://doi.org/10.1115/PVP2018-84385

Abstract

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Topics: Ductile-brittle transition , Fracture (Materials) , Fracture (Process) , Temperature , Electromagnetic scattering , Flat plates , Brittleness , Damage mechanics , Ductile fracture , Evaluation methods

Analysis of a Weld Overlay to Address Fatigue Cracking in a Stainless Steel Nozzle

S. E. Marlette, A. Udyawar, J. Broussard

PVP 2018; V01AT01A058doi:https://doi.org/10.1115/PVP2018-84722

Abstract

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Topics: Fatigue cracks , Nozzles , Overlays (Materials engineering) , Stainless steel , Maintenance , Design , Pressurized water reactors , Cracking (Materials) , Fracture (Process) , Pipes

Reactor Vessel Nozzle Inner Radius Fracture Analyses Using Elastic-Plastic Fracture Mechanics

S. E. Marlette

PVP 2018; V01AT01A059doi:https://doi.org/10.1115/PVP2018-85130

Abstract

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Topics: Fracture mechanics , Nozzles , Radius fractures , Reactor vessels , Design , ASME Standards , Fracture (Materials) , Fracture (Process) , Inspection , Mechanical engineers

International Session for Fast Reactor Design and Construction

Efficiency Diagram Alternative Rule for Ratchetting: Historical Background, Overview, On-Going Developments

A. Martin, C. Pétesch, Y. Lejeail, P. Lamagnère, T. Lebarbé, J. E. Muñoz Garcia, G. Aiello

PVP 2018; V01AT01A060doi:https://doi.org/10.1115/PVP2018-84161

Abstract

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Topics: Construction , Creep , Damage , Design , High temperature , Vacuum , Vessels

Development of a Program for High-Temperature Design Analysis and Defect Assessment According to RCC-MRx

Hyeong-Yeon Lee, Min-Gu Won, Nam-Su Huh, Woo-Gon Kim

PVP 2018; V01AT01A061doi:https://doi.org/10.1115/PVP2018-84242

Abstract

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Topics: Design , High temperature , Pipes , Computers , Fusion reactors , Heat exchangers , Pressure vessels , Temperature

2018 RCC-MRx Code Edition: Context, Overview, On-Going Developments

Cécile Pétesch, Thierry Lebarbé, Odile Gelineau, Damien Vallot, Martine Blat-Yrieix

PVP 2018; V01AT01A062doi:https://doi.org/10.1115/PVP2018-84706

Abstract

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Topics: Construction , Feedback , High temperature , Vacuum , Vessels , Workshops (Work spaces)

Master Curve Fracture Toughness and Other Small Specimen Mechanical Properties (Joint With MF-12)

A Perspective of the Small Punch Test Application to the Evaluation of Hydrogen Embrittlement in Steels: Effect of Punch Rate on Fracture Properties

B. Arroyo, J. A. Álvarez, F. Gutiérrez-Solana, J. Sainz, R. Lacalle

PVP 2018; V01AT01A063doi:https://doi.org/10.1115/PVP2018-84066

Abstract

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Topics: Fracture toughness , Hydrogen embrittlement , Steel , Computer simulation , Fracture (Materials) , Micromechanical devices , Stress

Interlaboratory Study for Small Punch Testing Preliminary Results

Milan Brumovsky, Radim Kopriva

PVP 2018; V01AT01A064doi:https://doi.org/10.1115/PVP2018-84142

Abstract

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Topics: Testing , ASTM International , Damage , Power stations

Estimation of the Reference Temperature, T₀, by Means of the Small Punch Testing Technique

David Andrés, Roberto Lacalle, Sergio Cicero, Jose A. Álvarez, Manuel Pinzón

PVP 2018; V01AT01A065doi:https://doi.org/10.1115/PVP2018-84250

Abstract

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Topics: Temperature , Testing , Embrittlement , Vessels , Dimensions , Irradiation (Radiation exposure) , Neutrons , Nuclear power stations , Steel

Assessment of Master Curve Material Inhomogeneity Using Small Data Sets

Kim Wallin

PVP 2018; V01AT01A066doi:https://doi.org/10.1115/PVP2018-84297

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Fracture Toughness Evaluation of Heat-Affected Zone Under Weld Overlay Cladding in Reactor Pressure Vessel Steel

Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Satoshi Hanawa, Yutaka Nishiyama

PVP 2018; V01AT01A067doi:https://doi.org/10.1115/PVP2018-84535

Abstract

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Topics: Cladding systems (Building) , Fracture toughness , Heat , Overlays (Materials engineering) , Reactor vessels , Steel , Strips , Base metals , Pressure vessels , Temperature

Crack Resistance Curve Measurement With Miniaturized CT Specimen

Rachid Chaouadi, Marlies Lambrecht, Robert Gérard

PVP 2018; V01AT01A068doi:https://doi.org/10.1115/PVP2018-84690

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Topics: Fracture (Materials) , Size effect , Geometry , Steel , Tension , ASTM International , Dimensional analysis , Electromagnetic scattering , Fracture mechanics , Phase transition temperature

Master Curve Testing on Reconstituted Surveillance Charpy Specimens

Ferenc Gillemot, Márta Horváth, Ákos Horváth, Ildikó Szenthe, Attila Kovács

PVP 2018; V01AT01A069doi:https://doi.org/10.1115/PVP2018-84749

Abstract

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Topics: Surveillance , Testing , Fracture toughness , Embrittlement , Fracture (Materials) , Radiation (Physics) , Chain , Displacement , Evaluation methods , Fracture mechanics

Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Before and After Irradiation

Mikhail A. Sokolov

PVP 2018; V01AT01A070doi:https://doi.org/10.1115/PVP2018-84804

Abstract

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Topics: Fracture toughness , Irradiation (Radiation exposure) , ASTM International , Geometry , Reactor vessels , Temperature

Evaluation of Through Wall Fracture Toughness Distribution of IAEA Reference Material JRQ by Mini-C(T) Specimens and the Master Curve Method

Masato Yamamoto, Tomohiro Kobayashi

PVP 2018; V01AT01A071doi:https://doi.org/10.1115/PVP2018-84889

Abstract

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Topics: Fracture toughness , Temperature , Fluence (Radiation measurement) , Fracture (Materials) , Reactor vessels , Regulations , Stress , Thermal shock , Wall thickness

Trial Study of the Master Curve Fracture Toughness Evaluation by Mini-C(T) Specimens for Low Upper Shelf Weld Metal Linde-80

Masato Yamamoto

PVP 2018; V01AT01A072doi:https://doi.org/10.1115/PVP2018-84906

Abstract

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Topics: Fracture toughness , Metals , Temperature , Ductile fracture , Electromagnetic scattering , Forging , Irradiation (Radiation exposure) , Manufacturing , Reactor vessels , Steel

Inter-Laboratory Results and Analyses of Mini-C(T) Specimen Testing of an Irradiated Linde 80 Weld Metal

William Server, Mikhail Sokolov, Masato Yamamoto, Robert Carter

PVP 2018; V01AT01A073doi:https://doi.org/10.1115/PVP2018-84950

Abstract

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Topics: Metals , Testing , Fracture toughness , ASTM International , Ductile fracture , Fracture (Materials) , Fracture (Process) , Low temperature , Reactor vessels , Temperature

Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Using Mini-C(T) Specimens

Michael R. Ickes, J. Brian Hall, Robert G. Carter

PVP 2018; V01AT01A074doi:https://doi.org/10.1115/PVP2018-84967

Abstract

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Topics: Fracture toughness , Reactor vessels , ASTM International , Displacement , Geometry , Irradiation (Radiation exposure) , Metals , Surveillance

Study on Applicability of Master Curve Methodology Using Miniature C(T) Specimen to a Reactor Pressure Vessel With Low Upper Shelf Energy

Kentaro Yoshimoto, Takatoshi Hirota, Hiroyuki Sakamoto, Masato Oshikiri, Kazuya Tsutsumi, Takeshi Murakami

PVP 2018; V01AT01A075doi:https://doi.org/10.1115/PVP2018-84994

Abstract

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Topics: Reactor vessels , Fracture toughness , Irradiation (Radiation exposure) , Neutrons , Steel , Countermeasures , Ductile fracture , Embrittlement , Fracture (Materials) , Fracture (Process)

Master Curve Fracture Toughness Characterization of Eurofer97 Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications

Xiang Chen, Mikhail A. Sokolov, Yutai Katoh, Michael Rieth, Logan N. Clowers

PVP 2018; V01AT01A076doi:https://doi.org/10.1115/PVP2018-85065

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Topics: Fracture toughness , Steel , Irradiation (Radiation exposure) , Temperature , Testing , ASTM International , Damage , Dimensions , Electromagnetic scattering , Embrittlement

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Master Curve Fracture Toughness and Other Small Specimen Mechanical Properties (Joint With MF-12)

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