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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
View Paper titled, Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals
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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

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
View Paper titled, Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld
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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
View Paper titled, Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor
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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
View Paper titled, On the Effect of Hot-Box Size on Coke Drum Skirt Fatigue Life
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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
View Paper titled, Towards a Probabilistic Analysis of Pressurized Thermal Shock
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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
View Paper titled, Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations
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Topics: Accidents, Boiling water reactors, Creep, Damage, Physics, Radiation (Physics), Simulation, Thermal hydraulics
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
View Paper titled, A Numerical Approach to Correlate Compression Stress Relaxation and Compression Set of Elastomer O-Rings With Tightness
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Topics: Compression, Compressive stress, Elastomers, Relaxation (Physics), Seals, Finite element model, Leakage, Flanges, Mechanical properties, Temperature
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
View Paper titled, Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
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Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon
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
View Paper titled, Outcomes of Three Large Scale Fire Reference Tests Conducted in BAM Fire Test Facility
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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
View Paper titled, Numerical Modelling of Compression Stress Relaxation and Compression Set of Elastomer O-Ring During Aging
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Topics: Compression, Compressive stress, Elastomers, Modeling, Relaxation (Physics), Seals, Temperature, Containers, Mechanical properties, Radioactive substances
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
View Paper titled, Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK
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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
View Paper titled, A Study of Flexible Magnetic Camera for Welded Tubular Joint Inspection
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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
View Paper titled, Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA
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Topics: Damage, Laser welding, Neutrons, Stainless steel, Helium, Welding, Heat, Welded joints, Cracking (Materials), Fracture (Process)
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
View Paper titled, Temperature Prediction of a TN-32 Used Nuclear Fuel Canister Subjected to Vacuum Drying Conditions
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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

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
View Paper titled, Failure Analysis of Furnace Tube in the Radiation Section of Ethylene Cracking Furnace
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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
View Paper titled, Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI
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Topics: Control systems, Cracking (Materials), Creep, Design, Dimensions, Embrittlement, Failure, Ferrites (Magnetic materials), Fracture (Process), Fracture mechanics
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
View Paper titled, Master Curve Testing on Reconstituted Surveillance Charpy Specimens
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Topics: Surveillance, Testing, Fracture toughness, Embrittlement, Fracture (Materials), Radiation (Physics), Chain, Displacement, Evaluation methods, 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
View Paper titled, Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition
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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

Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels

Takuya Ogawa, J. Brian Hall, Benjamin E. Mays, Timothy C. Hardin
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A009, July 16–20, 2017
Paper No: PVP2017-65317
DOI: https://doi.org/10.1115/PVP2017-65317
View Paper titled, Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels
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Topics: Reactor vessels, Steel, ASTM International, Databases, Copper, Embrittlement, Irradiation (Radiation exposure), Light water reactors, Surveillance, Chemistry
Proceedings Papers

Behavior of Wood Filled Impact Limiters During the IAEA Thermal Test

Martin Feldkamp, Marina Erenberg, Marko Nehrig, Claus Bletzer, André Musolff, Thorsten Schönfelder, Frank Wille
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A038, July 16–20, 2017
Paper No: PVP2017-65721
DOI: https://doi.org/10.1115/PVP2017-65721
View Paper titled, Behavior of Wood Filled Impact Limiters During the IAEA Thermal Test
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Topics: Wood products, Damage, Safety, Combustion, Cushioning materials, Containment, Fire, Fire testing, Mechanical testing, Radioactive substances