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Proceedings Papers

Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry

Raul B. Rebak, Liang Yin, Michael Larsen, Rajnikant V. Umretiya, Andrew K. Hoffman

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A017, July 17–22, 2022

Paper No: PVP2022-80559

DOI: https://doi.org/10.1115/PVP2022-80559

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Topics: Cladding systems (Building), Corrosion, Fuels, Light water reactors, Water chemistry

Proceedings Papers

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Adam Griffiths, Peter Gill, Ben Coult, Jack Beswick, Norman Platts, Jonathan Mann, Chris Currie, Joe Airey

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A013, July 13–15, 2021

Paper No: PVP2021-62909

DOI: https://doi.org/10.1115/PVP2021-62909

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Topics: Fatigue, Fracture (Materials), Stainless steel, Testing, Grain size, Heat, Nucleation (Physics), Stress, Analytical methods, ASME Standards

Proceedings Papers

Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels

Ben Coult, Adam Griffiths, Jack Beswick, Peter Gill, Norman Platts, Jean Smith, Gary Stevens

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A016, August 3, 2020

Paper No: PVP2020-21406

DOI: https://doi.org/10.1115/PVP2020-21406

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Topics: Fatigue testing, Fracture (Materials), Stainless steel, Testing, Fatigue, Nucleation (Physics), Stress, Analytical methods, ASME Standards, Bridges (Structures)

Proceedings Papers

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A080, August 3, 2020

Paper No: PVP2020-21670

DOI: https://doi.org/10.1115/PVP2020-21670

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Topics: Finite element analysis, Surface cracks, Welded joints, Fracture (Materials), Fracture (Process), Shapes, Fitness-for-service, Metals, Stainless steel, Base metals

Proceedings Papers

Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment

Sampath Ranganath, Robert G. Carter, Rajeshwar Pathania, Stefan Ritter, Hans-Peter Seifert

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A011, July 15–20, 2018

Paper No: PVP2018-84257

DOI: https://doi.org/10.1115/PVP2018-84257

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Topics: Alloy steel, Boiling water reactors, Stress corrosion cracking, Vessels, Fracture (Materials), Nozzles, Water chemistry, Cracking (Materials), Fracture (Process), Hydrogen

Proceedings Papers

Effect of Uncontrolled Hydrogen Injection on SCC Susceptibility of 304L Steel in High Temperature Water

A. L. Medina-Almazán, G. Galicia-Aguilar, J. C. Zenteno-Suárez, C. Arganis-Juárez, N. López-García, M. Marín-Almazo

Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A032, July 16–20, 2017

Paper No: PVP2017-65040

DOI: https://doi.org/10.1115/PVP2017-65040

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Topics: High temperature, Hydrogen, Steel, Water, Boiling water reactors, Brittleness, Corrosion, Fatigue cracks, Light water reactors, Nuclear power stations

Proceedings Papers

Effects of Hot Water and Holds on Fatigue of Stainless Steel

Jussi Solin, Jouni Alhainen, Ertugrul Karabaki, Wolfgang Mayinger

Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A021, July 17–21, 2016

Paper No: PVP2016-63291

DOI: https://doi.org/10.1115/PVP2016-63291

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Topics: Fatigue, Hot water, Stainless steel, Temperature, Water, Nuclear power stations, Pressurized water reactors, Steel, Atoms, Circuits

Proceedings Papers

Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments

Ernest D. Eason, Raj Pathania

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A075, July 19–23, 2015

Paper No: PVP2015-45323

DOI: https://doi.org/10.1115/PVP2015-45323

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Topics: Irradiation (Radiation exposure), Light water reactors, Stainless steel, Stress corrosion cracking, Boiling water reactors, Fittings, Fracture (Materials), Pressurized water reactors, Water chemistry, ASME Standards

Proceedings Papers

A Bayesian-Probabilistic Framework for Real-Time Fatigue Usage Factor Monitoring of Nuclear Reactor Components

Subhasish Mohanty, William Iverson, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan

Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A043, July 19–23, 2015

Paper No: PVP2015-45848

DOI: https://doi.org/10.1115/PVP2015-45848

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Topics: Fatigue, Nuclear reactors, Pressurized water reactors, Stress, Fatigue life, Stainless steel, Temperature, Water chemistry

Proceedings Papers

Weld Residual Stress Analysis and Axial PWSCC Predictions in a Double Vee Groove Large Diameter Nozzle

Frederick W. Brust, E. Punch, D. J. Shim, David Rudland, Howard Rathbun

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A089, July 14–18, 2013

Paper No: PVP2013-98065

DOI: https://doi.org/10.1115/PVP2013-98065

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Topics: Nozzles, Stress analysis (Engineering), Fracture (Materials), Welded joints, Pressurized water reactors, Metals, Pipes, Residual stresses, Stainless steel, Alloys

Proceedings Papers

Modeling Crack Growth in Weld Residual Stress Fields Using the Finite Element Alternating Method

F. W. Brust, T. Zhang, D.-J. Shim, G. Wilkowski, D. Rudland

Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 1643-1649, July 17–21, 2011

Paper No: PVP2011-57935

DOI: https://doi.org/10.1115/PVP2011-57935

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Topics: Finite element analysis, Fracture (Materials), Modeling, Stress, Welded joints, Nozzles, Pressurized water reactors, Metals, Pipes, Stainless steel

Proceedings Papers

PWSCC Crack Growth Modeling Approaches

F. W. Brust, D.-J. Shim, G. Wilkowski, D. Rudland

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 139-145, July 17–21, 2011

Paper No: PVP2011-57974

DOI: https://doi.org/10.1115/PVP2011-57974

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Topics: Fracture (Materials), Modeling, Nozzles, Welded joints, Pressurized water reactors, Stress, Metals, Pipes, Residual stresses, Stainless steel

Proceedings Papers

Examination of Factors in the Modified Rate Approach Method Under Various Conditions

Yuichi Fukuta, Seiji Asada, Yuichiro Nomura, Hiroshi Kanasaki

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 247-256, July 17–21, 2011

Paper No: PVP2011-57435

DOI: https://doi.org/10.1115/PVP2011-57435

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Topics: Fatigue, Fatigue damage, Fatigue life, Temperature, Water, Water chemistry

Proceedings Papers

Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRS

Jong-Dae Hong, Changheui Jang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 5, 327-333, July 18–22, 2010

Paper No: PVP2010-25176

DOI: https://doi.org/10.1115/PVP2010-25176

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Topics: Alloys, Fracture mechanics, Pressurized water reactors, Welded joints, Fracture (Materials), Failure, Probability, Water chemistry, Cracking (Materials), Fracture (Process)

Proceedings Papers

Inspection of Piping Wall Loss With Flow Accelerated Corrosion Accelerated Simulation Test

Kyung Ha Ryu, Ji Hak Kim, Il Soon Hwang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1233-1241, July 18–22, 2010

Paper No: PVP2010-25501

DOI: https://doi.org/10.1115/PVP2010-25501

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Topics: Corrosion, Flow (Dynamics), Inspection, Pipes, Simulation, Carbon steel, Nuclear power stations, Piping systems, Temperature, Water chemistry

Proceedings Papers

Quantifying the Crack Tip Oxidation Kinetics Parameters and Their Contribution to Stress Corrosion Cracking in High Temperature Water

Tetsuo Shoji, Zhanpeng Lu, He Xue, Yubing Qiu, Kazuhiko Sakaguchi

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 657-674, July 18–22, 2010

Paper No: PVP2010-25238

DOI: https://doi.org/10.1115/PVP2010-25238

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Topics: Fracture (Materials), High temperature, Oxidation, Stress corrosion cracking, Water, Alloys, Water chemistry, Boiling, Chemistry, Pressurized water reactors

Proceedings Papers

Summary of Weld Residual Stress Analyses for Dissimilar Metal Weld Nozzles

F. W. Brust, Tao Zhang, Do-Jun Shim, Sureshkumar Kalyanam, Gery Wilkowski, Mike Smith, Andrew Goodfellow

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1521-1529, July 18–22, 2010

Paper No: PVP2010-26106

DOI: https://doi.org/10.1115/PVP2010-26106

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Topics: Metals, Nozzles, Stress analysis (Engineering), Pressurized water reactors, Stress, Welded joints, Hardening, Stainless steel, Boilers, Constitutive equations

Proceedings Papers

Long Term Behaviour of Stuffing Box Packings Under the Influence of Fluids at High Temperature

Hans Kockelmann, Jaroslav Bartonicek, Eberhard Roos, Rolf Hahn, Werner Ottens

Proc. ASME. PVP2009, Volume 2: Computer Applications/Technology and Bolted Joints, 35-39, July 26–30, 2009

Paper No: PVP2009-77059

DOI: https://doi.org/10.1115/PVP2009-77059

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Topics: Fluids, High temperature, Packings (Cushioning), Stress, Graphite, Manufacturing, Springs, Cycles, Fibers, Friction

Proceedings Papers

Assessment of the Fatigue Life of a PWR Surge Line Including the Effect of Coolant Environment

Gu¨nter Ko¨nig, Jaroslav Bartonicek, Horst Rothenho¨fer

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 453-460, July 26–30, 2009

Paper No: PVP2009-77739

DOI: https://doi.org/10.1115/PVP2009-77739

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Topics: Coolants, Fatigue life, Pressurized water reactors, Surges, Design, Failure, Fatigue, Boundary-value problems, Corrosion, Damage

Proceedings Papers

Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks

A´gnes Ja´nosine´ Bi´ro´, Sa´ndor Ra´tkai, Ma´rton Osztheimer, Katalin Baumann-ne´ Tanits, Sa´ndor Baranya

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 393-402, July 26–30, 2009

Paper No: PVP2009-77504

DOI: https://doi.org/10.1115/PVP2009-77504

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Topics: Acceptance criteria, Boilers, Coolants, Corrective actions, Corrosion, Damage, Emergencies, Emergency core cooling systems, Erosion, Fasteners

NARROW

Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Results From Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment

Effect of Uncontrolled Hydrogen Injection on SCC Susceptibility of 304L Steel in High Temperature Water

Effects of Hot Water and Holds on Fatigue of Stainless Steel

Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments

A Bayesian-Probabilistic Framework for Real-Time Fatigue Usage Factor Monitoring of Nuclear Reactor Components

Weld Residual Stress Analysis and Axial PWSCC Predictions in a Double Vee Groove Large Diameter Nozzle

Modeling Crack Growth in Weld Residual Stress Fields Using the Finite Element Alternating Method

PWSCC Crack Growth Modeling Approaches

Examination of Factors in the Modified Rate Approach Method Under Various Conditions

Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRS

Inspection of Piping Wall Loss With Flow Accelerated Corrosion Accelerated Simulation Test

Quantifying the Crack Tip Oxidation Kinetics Parameters and Their Contribution to Stress Corrosion Cracking in High Temperature Water

Summary of Weld Residual Stress Analyses for Dissimilar Metal Weld Nozzles

Long Term Behaviour of Stuffing Box Packings Under the Influence of Fluids at High Temperature

Assessment of the Fatigue Life of a PWR Surge Line Including the Effect of Coolant Environment

Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks

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