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Proceedings Papers

Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld

Mikhail A. Sokolov

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A027, July 17–22, 2022

Paper No: PVP2022-84827

DOI: https://doi.org/10.1115/PVP2022-84827

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Topics: Embrittlement, Fracture toughness, Radiation (Physics)

Proceedings Papers

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

Henry Cathcart, James Finley, John Taylor, Alexander Frost

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022

Paper No: PVP2022-84742

DOI: https://doi.org/10.1115/PVP2022-84742

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Topics: Atoms, Bricks, Carbon, Dimensions, Emissions, Failure, Failure analysis, Finite element analysis, Fluence (Radiation measurement), Fuels

Proceedings Papers

On the Effect of Hot-Box Size on Coke Drum Skirt Fatigue Life

John Fernando, Henry Kwok, Leanne Wong, Luke Chan

Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A030, July 17–22, 2022

Paper No: PVP2022-84068

DOI: https://doi.org/10.1115/PVP2022-84068

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Topics: Coke, Fatigue life, Design, Shells, Temperature, Cycles, Emissivity, Failure, Fatigue, Fatigue failure

Proceedings Papers

Towards a Probabilistic Analysis of Pressurized Thermal Shock

C. D. Versteylen, N. B. Siccama, H. J. Uitslag-Doolaard, F. Brigante, E. Pallaoro, F. H. E. De Haan - De Wilde

Proc. ASME. PVP2022, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A015, July 17–22, 2022

Paper No: PVP2022-84287

DOI: https://doi.org/10.1115/PVP2022-84287

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Topics: Thermal shock, Fracture (Materials), Stress, Reactor vessels, Computational fluid dynamics, Simulation, Brittleness, Fluids, Probability, Finite element methods

Proceedings Papers

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

Jinya Katsuyama, Yoshihito Yamaguchi, Yoshiyuki Nemoto, Takuya Furuta, Yoshiyuki Kaji

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A030, July 17–22, 2022

Paper No: PVP2022-84609

DOI: https://doi.org/10.1115/PVP2022-84609

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Topics: Accidents, Boiling water reactors, Creep, Damage, Physics, Radiation (Physics), Simulation, Thermal hydraulics

Proceedings Papers

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A049, July 17–22, 2022

Paper No: PVP2022-84936

DOI: https://doi.org/10.1115/PVP2022-84936

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Topics: Compression, Finite element analysis, Irradiation (Radiation exposure), Reactor vessels, Stainless steel, Dislocation density, Materials properties, Stress-strain curves, Boundary-value problems, Constitutive equations

Proceedings Papers

A Numerical Approach to Correlate Compression Stress Relaxation and Compression Set of Elastomer O-Rings With Tightness

Mike Weber, Maha Zaghdoudi, Anja Kömmling, Matthias Jaunich, Dietmar Wolff

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A030, July 13–15, 2021

Paper No: PVP2021-61976

DOI: https://doi.org/10.1115/PVP2021-61976

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Topics: Compression, Compressive stress, Elastomers, Relaxation (Physics), Seals, Finite element model, Leakage, Flanges, Mechanical properties, Temperature

Proceedings Papers

Outcomes of Three Large Scale Fire Reference Tests Conducted in BAM Fire Test Facility

Martin Feldkamp, Thomas Quercetti, Frank Wille

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A038, August 3, 2020

Paper No: PVP2020-21245

DOI: https://doi.org/10.1115/PVP2020-21245

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Topics: Fire, Fire testing, Performance, Temperature, Heat, Accidents, Flux (Metallurgy), Flames, Radioactive substances, Steel sheet

Proceedings Papers

Numerical Modelling of Compression Stress Relaxation and Compression Set of Elastomer O-Ring During Aging

Maha Zaghdoudi, Mike Weber, Anja Kömmling, Matthias Jaunich, Dietmar Wolff

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A040, August 3, 2020

Paper No: PVP2020-21270

DOI: https://doi.org/10.1115/PVP2020-21270

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Topics: Compression, Compressive stress, Elastomers, Modeling, Relaxation (Physics), Seals, Temperature, Containers, Mechanical properties, Radioactive substances

Proceedings Papers

Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs

Maksym Zarazovskii, Volodymyr Revka, Liudmyla Chyrko

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A018, August 3, 2020

Paper No: PVP2020-21748

DOI: https://doi.org/10.1115/PVP2020-21748

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Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon

Proceedings Papers

Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK

Nicholas Underwood, Paul Nevitt, Andrew Howarth, Nicholas Barron

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A043, August 3, 2020

Paper No: PVP2020-21790

DOI: https://doi.org/10.1115/PVP2020-21790

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Topics: Advanced materials, Boiling, Carbon, Climate change, Construction, Cooling, Cooling systems, Cutting, Cycles, Design

Proceedings Papers

A Study of Flexible Magnetic Camera for Welded Tubular Joint Inspection

Eunho Choe, Hoyong Lee, Jinyi Lee

Proc. ASME. PVP2019, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 27th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD), V005T10A001, July 14–19, 2019

Paper No: PVP2019-93371

DOI: https://doi.org/10.1115/PVP2019-93371

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Topics: Inspection, Sensors, Tubular joints, Welding, Nondestructive evaluation, Shapes, Testing, Magnetic induction, Risk, Contamination

Proceedings Papers

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Paula D. Freyer, Jonathan K. Tatman, Frank A. Garner, Greg J. Frederick, Benjamin J. Sutton

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A087, July 14–19, 2019

Paper No: PVP2019-93316

DOI: https://doi.org/10.1115/PVP2019-93316

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Topics: Damage, Laser welding, Neutrons, Stainless steel, Helium, Welding, Heat, Welded joints, Cracking (Materials), Fracture (Process)

Proceedings Papers

Master Curve Testing on Reconstituted Surveillance Charpy Specimens

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

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A069, July 15–20, 2018

Paper No: PVP2018-84749

DOI: https://doi.org/10.1115/PVP2018-84749

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

Proceedings Papers

Failure Analysis of Furnace Tube in the Radiation Section of Ethylene Cracking Furnace

Wen Liu, GuoDong Sun, Jian Xing, Zhenlong Hu, Luowei Cao, Fakun Zhuang

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A009, July 15–20, 2018

Paper No: PVP2018-84037

DOI: https://doi.org/10.1115/PVP2018-84037

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Topics: Failure analysis, Fracture (Process), Furnaces, Radiation (Physics), Carburization, Pipes, Failure, Brittle fracture, Embrittlement, Fracture (Materials)

Proceedings Papers

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

Milan Brumovsky

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A056, July 15–20, 2018

Paper No: PVP2018-84140

DOI: https://doi.org/10.1115/PVP2018-84140

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

Proceedings Papers

Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition

Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh, Yun-Jae Kim, Young-Jin Oh, Jae-Boong Choi

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A030, July 15–20, 2018

Paper No: PVP2018-84578

DOI: https://doi.org/10.1115/PVP2018-84578

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Topics: High temperature, Pipes, Thermal stresses, Geometry, Heat transfer, Sodium fast reactors, Temperature distribution, Boundary-value problems, Convection, Finite element analysis

Proceedings Papers

Temperature Prediction of a TN-32 Used Nuclear Fuel Canister Subjected to Vacuum Drying Conditions

Megan Higley, Mustafa Hadj-Nacer, Miles Greiner

Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A041, July 15–20, 2018

Paper No: PVP2018-84844

DOI: https://doi.org/10.1115/PVP2018-84844

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Topics: Drying, Nuclear fuels, Temperature, Vacuum, Cladding systems (Building), Heat, Computational fluid dynamics, Engineering simulation, Helium, Pressurized water reactors

Proceedings Papers

Nuclear Power Plant Fires and Explosions: Part III — Hamaoka Piping Explosion

Robert A. Leishear

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A013, July 16–20, 2017

Paper No: PVP2017-66284

DOI: https://doi.org/10.1115/PVP2017-66284

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Topics: Explosions, Fire, Nuclear power stations, Pipes, Hydrogen, Accidents, Oxygen, Ignition, Nuclear reactors, Water hammer

Proceedings Papers

Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant

Thomas M. Rosseel, Mikhail A. Sokolov, Xiang Chen, Randy K. Nanstad

Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A059, July 16–20, 2017

Paper No: PVP2017-65090

DOI: https://doi.org/10.1115/PVP2017-65090

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Topics: Nuclear power stations, Base metals, Light water reactors, Mechanical properties, Atoms, Cutting, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Heat

NARROW

Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

On the Effect of Hot-Box Size on Coke Drum Skirt Fatigue Life

Towards a Probabilistic Analysis of Pressurized Thermal Shock

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

A Numerical Approach to Correlate Compression Stress Relaxation and Compression Set of Elastomer O-Rings With Tightness

Outcomes of Three Large Scale Fire Reference Tests Conducted in BAM Fire Test Facility

Numerical Modelling of Compression Stress Relaxation and Compression Set of Elastomer O-Ring During Aging

Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs

Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK

A Study of Flexible Magnetic Camera for Welded Tubular Joint Inspection

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Master Curve Testing on Reconstituted Surveillance Charpy Specimens

Failure Analysis of Furnace Tube in the Radiation Section of Ethylene Cracking Furnace

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

Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition

Temperature Prediction of a TN-32 Used Nuclear Fuel Canister Subjected to Vacuum Drying Conditions

Nuclear Power Plant Fires and Explosions: Part III — Hamaoka Piping Explosion

Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant

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