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Proceedings Papers

Inverse Conduction Method for Complex Thermal Loading

Timothy Gilman
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A024, July 17–22, 2022
Paper No: PVP2022-84913
DOI: 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
Paper No: PVP2022-84605
DOI: 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
Click here to open pdf in another window 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
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Testing, Vessels, Steel, Stress, Design, Power stations
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, Roman Cicero, Kevin Mottershead, Stephan Courtin, Zaiqing Que, Sergio Cicero
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A013, July 17–22, 2022
Paper No: PVP2022-84625
DOI: https://doi.org/10.1115/PVP2022-84625
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)
Click here to open pdf in another window PDF for INCEFA-SCALE (Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment - Focusing on Gaps Between Laboratory Data and Component-Scale)
Topics: Fatigue, Nuclear power stations, Safety
Proceedings Papers

Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles

Pierre Dulieu, Valéry Lacroix, Vratislav Mares, Larbi Arbaoui, Jean-Philippe Bournot
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A082, July 17–22, 2022
Paper No: PVP2022-79529
DOI: https://doi.org/10.1115/PVP2022-79529
View Paper titled, Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
Click here to open pdf in another window PDF for Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
Topics: Metals, Nozzles, Reactor vessels, Residual stresses, Stress, Welding, Heat, Simulation, Welded joints, Alloys
Proceedings Papers

Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant

Jianfeng Shi, Yuhua Cao, Di Jiao, Fa Yu, Yu Li, Jiayin Jiang, Jinyang Zheng
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A006, July 17–22, 2022
Paper No: PVP2022-84477
DOI: https://doi.org/10.1115/PVP2022-84477
View Paper titled, Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant
Click here to open pdf in another window PDF for Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant
Topics: Design, Design methodology, Engineering standards, Nuclear power stations, Pipes, Polyethylene pipes, Stress, Water, Cooling, Pipelines
Proceedings Papers

Comparison Between Different Calculation Methods for Determining Bolting-Up Torque Moments

Alexander Mutz, Manfred Schaaf, Stefan Hufnagel
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A019, July 17–22, 2022
Paper No: PVP2022-86163
DOI: https://doi.org/10.1115/PVP2022-86163
View Paper titled, Comparison Between Different Calculation Methods for Determining Bolting-Up Torque Moments
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Topics: Computational methods, Finite element analysis, Stress analysis (Engineering), Torque, Flanges, Gaskets, ASME Boiler and Pressure Vessel Code, Acceptance criteria, ASME Standards, Design
Proceedings Papers

Mechanical Performance Evaluation of the Printed Circuit Heat Exchanger Core Experiments Under Tension and Pressure Loading

Heramb P. Mahajan, Lucas Maciel, Gracious Ngaile, Tasnim Hassan
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A027, July 17–22, 2022
Paper No: PVP2022-81247
DOI: https://doi.org/10.1115/PVP2022-81247
View Paper titled, Mechanical Performance Evaluation of the Printed Circuit Heat Exchanger Core Experiments Under Tension and Pressure Loading
Click here to open pdf in another window PDF for Mechanical Performance Evaluation of the Printed Circuit Heat Exchanger Core Experiments Under Tension and Pressure Loading
Topics: Circuits, Creep, Diffusion bonding (Metals), Equipment performance, Heat exchangers, Pressure, Tension, Temperature, Design, Stress
Proceedings Papers

Investigations on the Failure Behavior of Specimens Containing Crack Fields Made by Additive Manufacturing

Ludwig Stumpfrock, Ulrich Weber, Stefan Weihe, Michael Seidenfuss, Linda Mally
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A053, July 17–22, 2022
Paper No: PVP2022-84666
DOI: https://doi.org/10.1115/PVP2022-84666
View Paper titled, Investigations on the Failure Behavior of Specimens Containing Crack Fields Made by Additive Manufacturing
Click here to open pdf in another window PDF for Investigations on the Failure Behavior of Specimens Containing Crack Fields Made by Additive Manufacturing
Topics: Additive manufacturing, Failure, Fracture (Materials), Damage mechanics, Computer simulation, Damage, Pressure, Shear (Mechanics), Stress, Brittleness
Proceedings Papers

Assessment of an Euler-Bernoulli Beam Model Coupled to CFD in Order to Perform Fluid-Structure Simulations

Daniele Vivaldi, Guillaume Ricciardi
Proc. ASME. PVP2022, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A002, July 17–22, 2022
Paper No: PVP2022-81755
DOI: https://doi.org/10.1115/PVP2022-81755
View Paper titled, Assessment of an Euler-Bernoulli Beam Model Coupled to CFD in Order to Perform Fluid-Structure Simulations
Click here to open pdf in another window PDF for Assessment of an Euler-Bernoulli Beam Model Coupled to CFD in Order to Perform Fluid-Structure Simulations
Topics: Computational fluid dynamics, Engineering simulation, Fluids, Simulation, Cylinders, Fluid structure interaction, Finite element model, Nuclear power stations, Vibration, Water
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
Paper No: PVP2022-84684
DOI: https://doi.org/10.1115/PVP2022-84684
View Paper titled, Crack Growth Simulation Using Iterative Crack-Tip Modeling Technique
Click here to open pdf in another window PDF for Crack Growth Simulation Using Iterative Crack-Tip Modeling Technique
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
Paper No: PVP2022-80690
DOI: 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
Click here to open pdf in another window PDF for Fracture in the Ductile-To-Brittle Transition Region of A Narrow-Gap Alloy 52 and Alloy 52 Dissimilar Metal Weld With Buttering
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
Paper No: PVP2022-83875
DOI: 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
Click here to open pdf in another window 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
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
Paper No: PVP2022-81652
DOI: 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
Click here to open pdf in another window PDF for Seismic Test Result (Static Load Test) of the Dynamic Functional Demand Valve for Nuclear Power Plant
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
Paper No: PVP2022-83745
DOI: https://doi.org/10.1115/PVP2022-83745
View Paper titled, Inelastic Response Evaluation Method of Equipment Considering Peak Broadening of Response Spectrum
Click here to open pdf in another window PDF for Inelastic Response Evaluation Method of Equipment Considering Peak Broadening of Response Spectrum
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
Paper No: PVP2022-83982
DOI: https://doi.org/10.1115/PVP2022-83982
View Paper titled, Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems
Click here to open pdf in another window PDF for Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems
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
Paper No: PVP2022-83675
DOI: https://doi.org/10.1115/PVP2022-83675
View Paper titled, Analytical Method for Evaluating a 4-Piece Retaining Ring
Click here to open pdf in another window PDF for Analytical Method for Evaluating a 4-Piece Retaining Ring
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
Paper No: PVP2022-84190
DOI: 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)
Click here to open pdf in another window PDF for Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants (Part 2)
Topics: Boiling water reactors, Nuclear power stations, Steam, Valves
Proceedings Papers

Statistical Analysis of Localized Corrosion in Service Water Piping

S. Parker, A. Roukema, Y. Patten
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A034, July 13–15, 2021
Paper No: PVP2021-61831
DOI: https://doi.org/10.1115/PVP2021-61831
View Paper titled, Statistical Analysis of Localized Corrosion in Service Water Piping
Click here to open pdf in another window PDF for Statistical Analysis of Localized Corrosion in Service Water Piping
Topics: Corrosion, Pipes, Statistical analysis, Water, Wall thickness, Carbon steel, Density, Nondestructive evaluation, Nuclear power stations, Shapes
Proceedings Papers

FRACTESUS Project: General Framework of Materials Selection and Testing Processes

Tomasz Brynk, Marlies Lambrecht, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Tom Petit
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A066, July 13–15, 2021
Paper No: PVP2021-61906
DOI: https://doi.org/10.1115/PVP2021-61906
View Paper titled, FRACTESUS Project: General Framework of Materials Selection and Testing Processes
Click here to open pdf in another window PDF for FRACTESUS Project: General Framework of Materials Selection and Testing Processes
Topics: Fracture toughness, Reactor vessels, Tension, Testing, Steel, Base metals, Computer simulation, Fracture mechanics, Materials testing, Nuclear power stations
Proceedings Papers

Research and Examination of Seismic Safety Evaluation and Function Maintenance for Important Equipment in Nuclear Facilities

Osamu Furuya, Satoshi Fujita, Hitoshi Muta, Yasuki Ohtori, Tatsuya Itoi, Shigeki Okamura, Keisuke Minagawa, Izumi Nakamura, Shigeru Fujimoto, Akihito Otani, Akemi Nishida, Tomoyoshi Watakabe
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A022, July 13–15, 2021
Paper No: PVP2021-61781
DOI: https://doi.org/10.1115/PVP2021-61781
View Paper titled, Research and Examination of Seismic Safety Evaluation and Function Maintenance for Important Equipment in Nuclear Facilities
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Topics: Maintenance, Nuclear power stations, Safety