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Proceedings Papers

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

Francis H. Ku, Steven L. McCracken
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A082, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84981
https://doi.org/10.1115/PVP2018-84981
View Paper titled, Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld
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Topics: Feedwater, Metals, Nozzles, Overlays (Materials engineering), Stress analysis (Engineering), Pressurized water reactors, Design, Water, Emergencies, Finite element analysis
Proceedings Papers

SCC Propagation Analyses in a Welded Joint Under Various Assumed Residual Stresses and Anisotropic SCC Propagation Law

Hiroshi Okada, Manabu Kikuchi, Masahiro Ono, Yasunori Yusa, Masayuki Kamaya
Proc. ASME. PVP2018, Volume 2: Computer Technology and Bolted Joints, V002T02A010, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84238
https://doi.org/10.1115/PVP2018-84238
View Paper titled, SCC Propagation Analyses in a Welded Joint Under Various Assumed Residual Stresses and Anisotropic SCC Propagation Law
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Topics: Anisotropy, Residual stresses, Welded joints, Metals, Pressurized water reactors, Stress, Engineering simulation, Finite element methods, Mechanical properties, Mesh generation
Proceedings Papers

Development of Structural Integrity Assessment Method for Flow-Induced Vibration of Reactor Internals in PWR

Hirokazu Sugiura, Shigeyuki Watanabe, Akihisa Iwasaki, Hideyuki Morita, Hideyuki Sakata, Yoshito Nishikawa
Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A006, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84473
https://doi.org/10.1115/PVP2018-84473
View Paper titled, Development of Structural Integrity Assessment Method for Flow-Induced Vibration of Reactor Internals in PWR
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Topics: Flow-induced vibrations, Pressurized water reactors, Turbulence, Computational fluid dynamics, Fluctuations (Physics), Pressure, Flow (Dynamics), Resonance ionization spectroscopy, Vibration, Vibration analysis
Proceedings Papers

Numerical Simulation on Flow Induced Vibration and Fretting Wear of a Steam Generator

Wei Tan, Kai Guo, Xiantao Fan, Yipeng Wang, Guorui Zhu, Liyan Liu
Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A003, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84347
https://doi.org/10.1115/PVP2018-84347
View Paper titled, Numerical Simulation on Flow Induced Vibration and Fretting Wear of a Steam Generator
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Topics: Boilers, Computer simulation, Flow-induced vibrations, Wear, Fluids, Modeling, Porous materials, Design, Dynamic analysis, Corrosion
Proceedings Papers

Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun
Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A019, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84152
https://doi.org/10.1115/PVP2018-84152
View Paper titled, Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident
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Topics: Accidents, Boilers, Feedwater, Pressurized water reactors, Stress, Transients (Dynamics), Pipes, Computational fluid dynamics, Flow (Dynamics), Simulation
Proceedings Papers

Effect of Clamping Failure on Flow Induced Vibration and Fretting Wear of Fuel Rods

Qi Huan-huan, Feng Zhi-peng, Xiong Fu-rui, Jiang Nai-bin, Huang Qian, Huang Xuan
Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A001, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84326
https://doi.org/10.1115/PVP2018-84326
View Paper titled, Effect of Clamping Failure on Flow Induced Vibration and Fretting Wear of Fuel Rods
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Topics: Failure, Flow-induced vibrations, Fuel rods, Wear, Flow (Dynamics), Excitation, Pressurized water reactors, Turbulence, Displacement, Fuels
Proceedings Papers

SCC Crack Growth Analysis for a Dissimilar Metal Weld Using Advanced FEA

Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A001, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84513
https://doi.org/10.1115/PVP2018-84513
View Paper titled, SCC Crack Growth Analysis for a Dissimilar Metal Weld Using Advanced FEA
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Topics: Finite element analysis, Fracture (Materials), Metals, Boiling water reactors, Fitness-for-service, Japan Society of Mechanical Engineers, Pressurized water reactors, Stress corrosion cracking, Anisotropy, Finite element model
Proceedings Papers

The Experimental Work in Support to ATLAS+ Project

Dominique Moinereau, Patrick Le Delliou, Anna Dahl, Yann Kayser, Szabolcs Szavai, Levente Tatar, Tobias Bolinder, Marta Serrano, Jacques Besson, Tomas Nicak, Kim Wallin, Stéphane Marie
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A077, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84697
https://doi.org/10.1115/PVP2018-84697
View Paper titled, The Experimental Work in Support to ATLAS+ Project
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Topics: Coolants, Design, Fracture mechanics, Materials characterization, Materials properties, Metals, Nuclear reactors, Pipes, Pressure, Pressurized water reactors
Proceedings Papers

The Fracture Toughness Properties of China Manufactured Reactor Pressure Vessel Steels in Transition Temperature Range

Kai Sun, Xiaoyong Wu, Guoyun Li, Bang Wen
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A030, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84110
https://doi.org/10.1115/PVP2018-84110
View Paper titled, The Fracture Toughness Properties of China Manufactured Reactor Pressure Vessel Steels in Transition Temperature Range
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Topics: China, Fracture toughness, Phase transition temperature, Reactor vessels, Steel, Construction, Fracture (Materials), Irradiation (Radiation exposure), Neutrons, Plant construction
Proceedings Papers

Comparison of Pressure-Temperature Limits for a Pressurized Water Reactor Pressure Vessel Considering Beltline and Extended Beltline Regions

Hsoung-Wei Chou, Yu-Yu Shen, Chin-Cheng Huang
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A031, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84145
https://doi.org/10.1115/PVP2018-84145
View Paper titled, Comparison of Pressure-Temperature Limits for a Pressurized Water Reactor Pressure Vessel Considering Beltline and Extended Beltline Regions
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Topics: Pressure, Pressure vessels, Pressurized water reactors, Temperature, Nozzles, Embrittlement, Neutrons, Vessels, ASME Standards, Finite element model
Proceedings Papers

Crack Growth Prediction for Cracked Dissimilar Metal Weld Joint in Pipe Under Large Seismic Cyclic Loading

Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A084, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85022
https://doi.org/10.1115/PVP2018-85022
View Paper titled, Crack Growth Prediction for Cracked Dissimilar Metal Weld Joint in Pipe Under Large Seismic Cyclic Loading
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Topics: Fracture (Materials), Metals, Pipes, Nuclear power stations, Welded joints, Evaluation methods, Alloys, Nickel, Seismic hazard assessment, Stainless steel
Proceedings Papers

NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs

Milan Brumovsky
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A050, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84139
https://doi.org/10.1115/PVP2018-84139
View Paper titled, NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs
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Topics: Nuclear power stations, Pipes, Reactor vessels, Corrosion, Failure, Pressurized water reactors, Safety, Water, Damage, Design
Proceedings Papers

Demonstrate ASME Section XI Appendix G Margins for Pressurized Water Reactor Inlet and Outlet Nozzle Corner Regions

Anees Udyawar, J. Brian Hall, Justin Webb, Alexandria Carolan
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A068, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84345
https://doi.org/10.1115/PVP2018-84345
View Paper titled, Demonstrate ASME Section XI Appendix G Margins for Pressurized Water Reactor Inlet and Outlet Nozzle Corner Regions
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Topics: Corners (Structural elements), Nozzles, Pressurized water reactors, Temperature, Pressure, Finite element analysis, Fracture toughness, Stress, Reactor vessels, Ductility
Proceedings Papers

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
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A017, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84251
https://doi.org/10.1115/PVP2018-84251
View Paper titled, Effect of Surface Condition on the Fatigue Life of Austenitic Stainless Steels in High Temperature Water Environments
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Topics: Fatigue life, High temperature, Stainless steel, Water, Design, Fatigue design, Finishes, Surface roughness, Accounting, Alloys
Proceedings Papers

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
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A019, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84301
https://doi.org/10.1115/PVP2018-84301
View Paper titled, Environmental Assisted Fatigue and EDF 900 MWe PWRs Fleet: Towards an Exemption of Environmental Effects Consideration for Secondary Circuit Components
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Topics: Circuits, Fatigue, Pressurized water reactors, Electric arc furnaces, Fatigue testing, Nuclear power stations, Alloys, Coolants, Design, Inspection
Proceedings Papers

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
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A026, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84879
https://doi.org/10.1115/PVP2018-84879
View Paper titled, Further Validation of the Strain-Life Weighted (SNW) F en Method for Plant Realistic Strain and Temperature Waveforms
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Topics: Temperature, Fatigue, Cycles, Pressurized water reactors, Water, Accounting, Coolants, Fatigue life, Nuclear power stations, Oxygen
Proceedings Papers

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

Arnaud Blouin, Mathieu Couvrat, Félix Latourte, Julian Soulacroix
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A054, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84601
https://doi.org/10.1115/PVP2018-84601
View Paper titled, Tensile Tests for Cast Stainless Steel: Evolution of the RCC-M Code
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Topics: Stainless steel, Electromagnetic scattering, Gages, Radiation scattering, Scattering (Physics), Tensile strength, Mechanical properties, Microscopy, Pressurized water reactors, Temperature
Proceedings Papers

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
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A020, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84346
https://doi.org/10.1115/PVP2018-84346
View Paper titled, ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)
Open the PDF for ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation) in another window
Topics: Licensing, Piping systems, Pressurized water reactors, Fatigue, Transients (Dynamics), Cycles, In-service inspection, Inspection, Construction, Design
Proceedings Papers

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

Peter Gill, Norman Platts, Chris Currie, Eleanor Grieveson
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A027, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84923
https://doi.org/10.1115/PVP2018-84923
View Paper titled, A Thermomechanical PWR Test Facility to Investigate Thermal Shock Loading on a Small Scale Tubular Specimen
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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
Proceedings Papers

Evaluation of Risk From Carbon Macro-Segregation in Large Pressure Retaining Forged Nuclear Components

Ronald Gamble, Timothy Hardin
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A059, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84620
https://doi.org/10.1115/PVP2018-84620
View Paper titled, Evaluation of Risk From Carbon Macro-Segregation in Large Pressure Retaining Forged Nuclear Components
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Topics: Carbon, Pressure, Risk assessment, Pressurized water reactors, Forgings (Products), Fracture (Materials), Fracture (Process), Risk, Failure, Safety