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Proceedings Papers

Experimental Analysis of Dynamic Operations of the Main Steam Relief Isolation Valve Used in Nuclear Power Plants

Weihao Zhou, Chaoyong Zong, Qingye Li, Songzhi Jiang, Yanliang Liu, Xueguan Song
Proc. ASME. PVP2023, Volume 6: Operations, Applications, & Components, V006T07A015, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106855
https://doi.org/10.1115/PVP2023-106855
View Paper titled, Experimental Analysis of Dynamic Operations of the Main Steam Relief Isolation Valve Used in Nuclear Power Plants
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Topics: Experimental analysis, Nuclear power stations, Steam, Valves
Proceedings Papers

Development of Prediction Tool for Flow-Accelerated Corrosion: (2) Evaluation of Geometry Factor for Various Pipe Components

Tomohisa Yuasa, Shun Watanabe, Kimitoshi Yoneda, Ryo Morita
Proc. ASME. PVP2023, Volume 6: Operations, Applications, & Components, V006T07A005, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105401
https://doi.org/10.1115/PVP2023-105401
View Paper titled, Development of Prediction Tool for Flow-Accelerated Corrosion: (2) Evaluation of Geometry Factor for Various Pipe Components
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Topics: Computational fluid dynamics, Corrosion, Flow (Dynamics), Geometry, Nuclear power stations, Pipes
Proceedings Papers

Generation of a Fatigue Design Curve Suitable for Use on Additive Manufacture Nuclear Plant Components Produced From 316LN Stainless Steel Using Laser Powder Bed Fusion

William Press, Jay Ferriday, Thomas Jones, Matthew Dear, David Poole
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A001, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106379
https://doi.org/10.1115/PVP2023-106379
View Paper titled, Generation of a Fatigue Design Curve Suitable for Use on Additive Manufacture Nuclear Plant Components Produced From 316LN Stainless Steel Using Laser Powder Bed Fusion
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Topics: Fatigue design, Lasers, Nuclear power stations, Stainless steel, Fatigue, Stress, Valves, Design, Safety, Testing
Proceedings Papers

Seismic Design Method of Crossover Piping Across Building Isolation Boundary

Kenichi Shibukuwa
Proc. ASME. PVP2023, Volume 7: Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V007T08A022, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107170
https://doi.org/10.1115/PVP2023-107170
View Paper titled, Seismic Design Method of Crossover Piping Across Building Isolation Boundary
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Topics: Earthquake resistant design, Pipes, Earthquakes, Evaluation methods, Nuclear power stations, Buckling, Cycles, Design, Design methodology, Failure
Proceedings Papers

Uncertainties in In-Structure Response Spectra Due to Uncertainties in Input Motion Amplitude and Phase Spectra

Jinsuo R. Nie, Jim Xu, Vladimir Graizer, Dogan Seber
Proc. ASME. PVP2023, Volume 7: Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V007T08A016, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105307
https://doi.org/10.1115/PVP2023-105307
View Paper titled, Uncertainties in In-Structure Response Spectra Due to Uncertainties in Input Motion Amplitude and Phase Spectra
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Topics: Spectra (Spectroscopy), Spectral energy distribution, Uncertainty, Algorithms, Engineering standards, Nuclear power stations, Wavelets
Proceedings Papers

Study on Analysis Procedure Using Integrated Three-Dimensional FE Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups

Takehiro Kawashima, Yasutaka Kumagai, Yuki Asao, Shota Shimazu, Takuya Nishimura
Proc. ASME. PVP2023, Volume 7: Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V007T08A019, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107126
https://doi.org/10.1115/PVP2023-107126
View Paper titled, Study on Analysis Procedure Using Integrated Three-Dimensional FE Model for Reactor Coolant System by Applying to Shaking Table Tests for Scaled Mock-Ups
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Topics: Finite element model, Nuclear reactor coolants, Stress, Finite element analysis, Reactor vessels, Stress analysis (Engineering), Computers, Evaluation methods, Nuclear power stations, Pressurized water reactors
Proceedings Papers

INCEFA-SCALE (Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment - Focusing on Gaps Between Laboratory Data and Component-Scale)

Alec McLennan, Román Cicero, Jack Beswick, Stéphan Courtin, Zaiqing Que, Sergio Cicero
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A008, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105357
https://doi.org/10.1115/PVP2023-105357
View Paper titled, INCEFA-SCALE (Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment - Focusing on Gaps Between Laboratory Data and Component-Scale)
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Topics: Fatigue, Nuclear power stations, Safety, Stainless steel
Proceedings Papers

INCEFA-SCALE Project – Overview of the Modelling Plans

Stephan Courtin, Olivier Ancelet, Jack Beswick, Oliver Blakesley, Roman Cicero
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A012, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-101351
https://doi.org/10.1115/PVP2023-101351
View Paper titled, INCEFA-SCALE Project – Overview of the Modelling Plans
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Topics: Data mining, Fatigue, Modeling, Electric arc furnaces, Fatigue damage, Design, Finite element analysis, Nuclear power stations, Numerical analysis, Pressurized water reactors
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A037, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105707
https://doi.org/10.1115/PVP2023-105707
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading
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Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Steel, Testing, Vessels, Stress, Design, Yield stress
Proceedings Papers

Advancing the State-of-the-Art for Fretting Wear Testing

Salim El Bouzidi, Fabrice Guerout, Paul Feenstra, Anne McLellan, Brendan St. Pierre
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A006, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105842
https://doi.org/10.1115/PVP2023-105842
View Paper titled, Advancing the State-of-the-Art for Fretting Wear Testing
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Topics: Vibration, Wear, Wear testing, High temperature, Testing, Excitation, Boilers, Chalk, Chemistry, Data acquisition
Proceedings Papers

Crack Growth Simulation Using Iterative Crack-Tip Modeling Technique

Gi-Bum Lee, Youn-Young Jang, Nam-Su Huh, Sung-Hoon Park, Noh-Hwan Park, Jun Park, Kyoungsoo Park
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A001, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84684
https://doi.org/10.1115/PVP2022-84684
View Paper titled, Crack Growth Simulation Using Iterative Crack-Tip Modeling Technique
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Topics: Crack propagation, Fatigue cracks, Fracture (Materials), Modeling, Simulation, Nuclear power stations, Finite element analysis, Failure mechanisms, Fracture mechanics, Pipelines
Proceedings Papers

Fracture in the Ductile-To-Brittle Transition Region of A Narrow-Gap Alloy 52 and Alloy 52 Dissimilar Metal Weld With Buttering

Sebastian Lindqvist, Noora Hytönen, Laura Sirkiä, Pentti Arffman, Jari Lydman, Yanling Ge, Pekka Nevasmaa, Zaiqing Que
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A040, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-80690
https://doi.org/10.1115/PVP2022-80690
View Paper titled, Fracture in the Ductile-To-Brittle Transition Region of A Narrow-Gap Alloy 52 and Alloy 52 Dissimilar Metal Weld With Buttering
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Topics: Alloys, Brittleness, Fracture (Materials), Metals, Fracture toughness, Alloy steel, ASTM International, Fractography, Heat, Metallography
Proceedings Papers

Application of Small Punch Testing Methods for Thermal Ageing Assessment at Steam-Generators Materials From Decommissioned V1 NPP to LTO Support on VVER Type Units in Slovakia

Jana Petzova, Marek Adamech, David Slnek
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A047, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83875
https://doi.org/10.1115/PVP2022-83875
View Paper titled, Application of Small Punch Testing Methods for Thermal Ageing Assessment at Steam-Generators Materials From Decommissioned V1 NPP to LTO Support on VVER Type Units in Slovakia
Open the PDF for Application of Small Punch Testing Methods for Thermal Ageing Assessment at Steam-Generators Materials From Decommissioned V1 NPP to LTO Support on VVER Type Units in Slovakia in another window
Topics: Boilers, Nuclear decommissioning, Nuclear power stations, Testing
Proceedings Papers

Seismic Test Result (Static Load Test) of the Dynamic Functional Demand Valve for Nuclear Power Plant

Yoshinao Matsubara, Yoshitaka Tsutsumi, Urara Watanabe, Shota Tanemura, Yoshiaki Takemoto
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A002, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-81652
https://doi.org/10.1115/PVP2022-81652
View Paper titled, Seismic Test Result (Static Load Test) of the Dynamic Functional Demand Valve for Nuclear Power Plant
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Topics: Maintenance, Nuclear power stations, Stress, Valves
Proceedings Papers

Inelastic Response Evaluation Method of Equipment Considering Peak Broadening of Response Spectrum

Ichiro Tamura, Takuma Iwamoto, Yusuke Minakawa, Naotomo Maruyama, Masaki Tsuruki
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A012, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83745
https://doi.org/10.1115/PVP2022-83745
View Paper titled, Inelastic Response Evaluation Method of Equipment Considering Peak Broadening of Response Spectrum
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Topics: ASME Boiler and Pressure Vessel Code, Evaluation methods, Materials properties, Nuclear power stations, Piping systems, Soil, Uncertainty
Proceedings Papers

Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems

Sarah R. Suffield, Philip J. Jensen, William A. Perkins, Ben J. Jensen, Christopher L. Grant, Casey Spitz
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A025, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83982
https://doi.org/10.1115/PVP2022-83982
View Paper titled, Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems
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Topics: Particulate matter, Spent fuel storage, Stress corrosion cracking, Storage, Computational fluid dynamics, Modeling, Spent nuclear fuels, Heat, Inspection, Nuclear power
Proceedings Papers

Analytical Method for Evaluating a 4-Piece Retaining Ring

Alton Reich, Roberto DiSalvo
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A018, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83675
https://doi.org/10.1115/PVP2022-83675
View Paper titled, Analytical Method for Evaluating a 4-Piece Retaining Ring
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Topics: Analytical methods, Design, Nuclear power, Nuclear power stations, Pressure, Shapes, Valves
Proceedings Papers

Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants (Part 2)

Hideaki Itabashi, Yoshitaka Tsutsumi, Koji Nishino, Shin Kumagai, Ryo Kubota, Shota Tanemura
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A005, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84190
https://doi.org/10.1115/PVP2022-84190
View Paper titled, Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants (Part 2)
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Topics: Boiling water reactors, Nuclear power stations, Steam, Valves
Proceedings Papers

Inverse Conduction Method for Complex Thermal Loading

Timothy Gilman
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A024, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84913
https://doi.org/10.1115/PVP2022-84913
View Paper titled, Inverse Conduction Method for Complex Thermal Loading
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Topics: Fatigue, Heat conduction, Temperature, Fracture (Materials), Instrumentation, Flow (Dynamics), Stress, Thermocouples, Transfer functions, Algorithms
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A032, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84605
https://doi.org/10.1115/PVP2022-84605
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading in another window
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Testing, Vessels, Steel, Stress, Design, Power stations