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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

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A025, July 13–15, 2021

Paper No: PVP2021-61610

DOI: https://doi.org/10.1115/PVP2021-61610

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Topics: Modeling, Spent nuclear fuels, Structural dynamics, Fuels, Shock (Mechanics), Transportation systems, Boundary element methods, Buckling, Cladding systems (Building), Design

Proceedings Papers

Environmental Fatigue Screening for Subsequent License Renewal

Adam P. Walker, Gregory M. Imbrogno, Mark A. Gray, Charles A. Tomes

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A023, August 3, 2020

Paper No: PVP2020-21678

DOI: https://doi.org/10.1115/PVP2020-21678

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Topics: Fatigue, Licensing, Fatigue analysis, Cycles, Electric arc furnaces, Nuclear reactor coolants, Pressure, Transients (Dynamics), Water

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

Method for Comparison of Different Material Types in Environmental Fatigue Screening

Mark A. Gray, Jamie L. Oakman, Adam P. Walker

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A020, August 3, 2020

Paper No: PVP2020-21560

DOI: https://doi.org/10.1115/PVP2020-21560

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Topics: Electric arc furnaces, Fatigue, Licensing

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

Effect of Bending Load on Burst Pressure of Nuclear Power Plant Steam Generator Tubes With Uniform Wall Thinning

Michael C. Liu, Robert J. Gialdini, Russell C. Cipolla, Chang-Hoon Ha, Min-Ki Cho, Tae-Jung Park

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A104, July 14–19, 2019

Paper No: PVP2019-93758

DOI: https://doi.org/10.1115/PVP2019-93758

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Topics: Boilers, Nuclear power stations, Pressure, Stress, Accidents, Design, Maintenance, Licensing, Bending (Stress), Fracture (Materials)

Proceedings Papers

Overview of Current Practice for Analysis and Design of Independent Spent Fuel Storage Installation Pads

Gunup Kwon, Khaled Ata

Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A018, July 14–19, 2019

Paper No: PVP2019-93666

DOI: https://doi.org/10.1115/PVP2019-93666

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Topics: Design, Spent fuel storage, Spent nuclear fuels, Fuels, Slabs, Storage, Concretes, Earthquakes, Engineers, Licensing

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

Paper No: PVP2018-84346

DOI: https://doi.org/10.1115/PVP2018-84346

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Topics: Licensing, Piping systems, Pressurized water reactors, Fatigue, Transients (Dynamics), Cycles, In-service inspection, Inspection, Construction, Design

Proceedings Papers

Effects of Non-Normal Input Distributions and Sampling Region on Monte Carlo Results

Konstantinos Tsembelis, Seyun Eom, John Jin, Christopher Cole

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A002, July 15–20, 2018

Paper No: PVP2018-84767

DOI: https://doi.org/10.1115/PVP2018-84767

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Topics: Computers, Design, Failure, Fracture mechanics, Licensing, Nonlinear systems, Pressure, Probability, Transfer functions

Proceedings Papers

Long-Term Performance of Elastomer Seals: From Aging Tests to Lifetime Estimations

Matthias Jaunich, Anja Kömmling, Jutta Horn, Holger Völzke, Dietmar Wolff

Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A038, July 15–20, 2018

Paper No: PVP2018-84631

DOI: https://doi.org/10.1115/PVP2018-84631

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Topics: Elastomers, Licensing, Temperature, Transportation systems, Accidents, Containers, Containment, Irradiation (Radiation exposure), Leakage, Low temperature

Proceedings Papers

Proposed Review Framework for Design of Pressure Retaining Systems and Components (PRSC) in Small Modular Reactor (SMR)

Seyun Eom, Nabel Sadek, Khalid Chaudhry, Chris Cole, Raoul Awad, Xinjian Duan

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A073, July 15–20, 2018

Paper No: PVP2018-85106

DOI: https://doi.org/10.1115/PVP2018-85106

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Topics: Design, Pressure, Small modular reactors, Licensing, Coolants, Flux (Metallurgy), Industrial research, Neutrons, Nuclear industry, Nuclear reactors

Proceedings Papers

Component Testing Proposal to Quantify Margins in Existing Environmentally Assisted Fatigue (EAF) Requirements

D. A. Steininger, K. Wright, M. Twite, A. Morley, T. Métais, G. Léopold, J. C. Le Roux

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A014, July 16–20, 2017

Paper No: PVP2017-65995

DOI: https://doi.org/10.1115/PVP2017-65995

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Topics: Electric arc furnaces, Fatigue, Testing, Fatigue failure, Fracture (Materials), Boiling water reactors, Diluents, Fatigue life, Licensing, Nuclear power stations

Proceedings Papers

On-Site Vibration Test for Measuring Damping Ratio of PWR Reactor Coolant Loop

Takami Ishiguro, Takeshi Numata, Nobuyoshi Goshima, Masatsugu Monde, Hiroyuki Fuyama

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A008, July 16–20, 2017

Paper No: PVP2017-65047

DOI: https://doi.org/10.1115/PVP2017-65047

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Topics: Damping, Nuclear reactor coolants, Pressurized water reactors, Vibration tests, Earthquakes, Energy dissipation, Seismic analysis, Actuators, Boilers, Construction

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

Proceedings Papers

Testing and Numerical Simulation of Elastomers: From Specimen Tests to Simulation of Seal Behavior Under Assembly Conditions

Mike Weber, Anja Kömmling, Matthias Jaunich, Dietmar Wolff, Uwe Zencker, Holger Völzke, Dietmar Schulze, Ulrich Probst

Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A035, July 16–20, 2017

Paper No: PVP2017-65373

DOI: https://doi.org/10.1115/PVP2017-65373

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Topics: Computer simulation, Elastomers, Manufacturing, Simulation, Testing, Finite element analysis, Storage, Rubber, Spent nuclear fuels, Stress

Proceedings Papers

Comparison Between Test and Analysis for Spent Nuclear Fuel Transportation Cask

Woo-Seok Choi, Sangsoon Cho, Ki-Seog Seo, Kyoung-Sik Bang, Ju-Chan Lee, Seunghwan Yu

Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A040, July 16–20, 2017

Paper No: PVP2017-66084

DOI: https://doi.org/10.1115/PVP2017-66084

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Topics: Spent nuclear fuels, Transportation systems, Storage, Finite element model, Computer simulation, Concretes, Licensing, Modeling, Safety, Simulation

Proceedings Papers

Development of a Partial Structural Factor Approach for Direct Fracture Toughness Implementation Into the ASME Boiler and Pressure Vessel Code

Marjorie Erickson, Mark Kirk

Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A006, July 16–20, 2017

Paper No: PVP2017-66148

DOI: https://doi.org/10.1115/PVP2017-66148

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Topics: ASME Boiler and Pressure Vessel Code, Fracture toughness, Safety, Uncertainty, Fracture (Materials), Fracture (Process), Fracture mechanics, Brittle fracture, Electromagnetic scattering, Engineering standards

Proceedings Papers

Environmental Fatigue and Fatigue Monitoring System in Korea

Myung-Hwan Boo, Kyoung Soo Lee, Hyun-Su Kim, Chang-Kyun Oh

Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A039, July 17–21, 2016

Paper No: PVP2016-63374

DOI: https://doi.org/10.1115/PVP2016-63374

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Topics: Fatigue, Monitoring systems, Nuclear power stations, Design, Fatigue damage, Fatigue failure, Fatigue life, Licensing, Nuclear reactor coolants, Reliability

Proceedings Papers

Overview of EAF Screening Results on the 900 MWe NPP French Fleet

Thomas Métais, Nicolas Robert, Pierre Genette, Nicolas Etchegaray

Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A015, July 17–21, 2016

Paper No: PVP2016-63125

DOI: https://doi.org/10.1115/PVP2016-63125

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Topics: Electric arc furnaces, Nuclear power stations, Fatigue, Geometry, Heat transfer coefficients, Licensing, Power stations, Pressurized water reactors, Shock (Mechanics), Stress

2 3 4 5

NARROW

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

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Environmental Fatigue Screening for Subsequent License Renewal

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

Method for Comparison of Different Material Types in Environmental Fatigue Screening

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

Effect of Bending Load on Burst Pressure of Nuclear Power Plant Steam Generator Tubes With Uniform Wall Thinning

Overview of Current Practice for Analysis and Design of Independent Spent Fuel Storage Installation Pads

ASME Section XI Appendix L Flaw Tolerance Evaluation of Pressurized Water Reactor Piping Systems to Support Second License Renewal (80-Years Operation)

Effects of Non-Normal Input Distributions and Sampling Region on Monte Carlo Results

Long-Term Performance of Elastomer Seals: From Aging Tests to Lifetime Estimations

Proposed Review Framework for Design of Pressure Retaining Systems and Components (PRSC) in Small Modular Reactor (SMR)

Component Testing Proposal to Quantify Margins in Existing Environmentally Assisted Fatigue (EAF) Requirements

On-Site Vibration Test for Measuring Damping Ratio of PWR Reactor Coolant Loop

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

Testing and Numerical Simulation of Elastomers: From Specimen Tests to Simulation of Seal Behavior Under Assembly Conditions

Comparison Between Test and Analysis for Spent Nuclear Fuel Transportation Cask

Development of a Partial Structural Factor Approach for Direct Fracture Toughness Implementation Into the ASME Boiler and Pressure Vessel Code

Environmental Fatigue and Fatigue Monitoring System in Korea

Overview of EAF Screening Results on the 900 MWe NPP French Fleet

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