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Proceedings Papers

Research and Development of Viscous Fluid Dampers for Improvement of Seismic Resistance of Thermal Power Plants: Part 12 Vibration Measurement of Existing Boiler Structure

Keisuke Minagawa, Kiyoshi Aida, Satoshi Fujita

Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A008, July 17–22, 2022

Paper No: PVP2022-84633

DOI: https://doi.org/10.1115/PVP2022-84633

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Topics: Boilers, Dampers, Fluids, Industrial research, Thermal power stations, Vibration measurement, Earthquakes, Coal, Power stations, Carbon

Proceedings Papers

Dynamic Behavior of a Simplified Cantilever With Progressive Static Loading due to Ratchet Deformation

Satoru Kai, Naoto Kasahara, Masakazu Ichimiya

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A030, July 13–15, 2021

Paper No: PVP2021-61878

DOI: https://doi.org/10.1115/PVP2021-61878

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Topics: Cantilevers, Deformation, Failure mechanisms, Failure, Accidents, Excitation, Stress, Weight (Mass), Collapse, Cycles

Proceedings Papers

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Hitoshi Muta, Yasuki Ohtori, Osamu Furuya, Satoshi Fujita

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A021, July 13–15, 2021

Paper No: PVP2021-61742

DOI: https://doi.org/10.1115/PVP2021-61742

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Topics: Nuclear power stations, Reliability, Safety, Accidents, Design, Countermeasures, Fukushima nuclear disaster, Japan, 2011, Regulations, Defense industry, Earthquake risk

Proceedings Papers

Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing

Connor Woolum, D. Devin Imholte, Austin Fleming, David Kamerman, Korbin Tritthart

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A078, August 3, 2020

Paper No: PVP2020-21620

DOI: https://doi.org/10.1115/PVP2020-21620

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Topics: Accidents, Fuels, Irradiation (Radiation exposure), Manufacturing, Testing, Cladding systems (Building), Pressurized water reactors, Transients (Dynamics), Design, Fuel systems

Proceedings Papers

Modification to Shield Tank Overpressure Protection in a CANDU Reactor for Beyond Design Basis Event

Michael Huang, Khurram Khan, Ali Etedali-Zadeh, Jefferson Tse, Bing Li

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A023, July 14–19, 2019

Paper No: PVP2019-93026

DOI: https://doi.org/10.1115/PVP2019-93026

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Topics: Design, Overpressure protection, Water, Pipes, Vents, Containment, Heat, Pressure, Stress, ASME Boiler and Pressure Vessel Code

Proceedings Papers

Contribution to Safety Enhancement for BDBE in Structure and Material Fields

Naoto Kasahara, Takuya Sato, Andrei Blahoianu

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A047, July 15–20, 2018

Paper No: PVP2018-84353

DOI: https://doi.org/10.1115/PVP2018-84353

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Topics: Safety, Accidents, Failure mechanisms, Design, Failure, Fracture (Materials), Fracture (Process), Fukushima nuclear disaster, Japan, 2011, Probabilistic risk assessment, Risk

Proceedings Papers

Investigation of Fluid Diffusion Properties From Various Flaw Geometries of Piping

Shun Watanabe, Ryo Morita, Yuta Uchiyama

Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A021, July 15–20, 2018

Paper No: PVP2018-84212

DOI: https://doi.org/10.1115/PVP2018-84212

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Topics: Diffusion (Physics), Fluids, Pipes, Flow (Dynamics), Leakage, Maintenance, Regulations, Safety, Failure, Fracture (Materials)

Proceedings Papers

Difference of Strength Evaluation Approach Between for DBE and for BDBE

Naoto Kasahara, Takuya Sato

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A005, July 16–20, 2017

Paper No: PVP2017-65478

DOI: https://doi.org/10.1115/PVP2017-65478

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Topics: Accident management, Accidents, Countermeasures, Design, Elastic analysis, Failure, Failure mechanisms, Fukushima nuclear disaster, Japan, 2011, Inelastic analysis, Probabilistic risk assessment

Proceedings Papers

Nuclear Power Plant Fires and Explosions: Part I — Plant Designs and Hydrogen Ignition

Robert A. Leishear

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A014, July 16–20, 2017

Paper No: PVP2017-66285

DOI: https://doi.org/10.1115/PVP2017-66285

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Topics: Explosions, Fire, Hydrogen, Ignition, Nuclear power stations, Plant design, Pressurized water reactors, Accidents, Boiling water reactors, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986

Proceedings Papers

Nuclear Power Plant Fires and Explosions: Part II — Hydrogen Ignition Overview

Robert A. Leishear

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A011, July 16–20, 2017

Paper No: PVP2017-66278

DOI: https://doi.org/10.1115/PVP2017-66278

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Topics: Explosions, Fire, Hydrogen, Ignition, Nuclear power stations, Accidents, Water hammer, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Fukushima nuclear disaster, Japan, 2011, Pipes

Proceedings Papers

Nuclear Power Plant Fires and Explosions: Part IV — Water Hammer Explosion Mechanisms

Robert A. Leishear

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A012, July 16–20, 2017

Paper No: PVP2017-66279

DOI: https://doi.org/10.1115/PVP2017-66279

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Topics: Explosions, Fire, Nuclear power stations, Water hammer, Hydrogen, Oxygen, Pipes, Compression, Accidents, Combustion

Proceedings Papers

The OECD-NEA Programme on Metallic Component Margins Under High Seismic Loads (MECOS): Towards New Criteria

Pierre Sollogoub

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A029, July 16–20, 2017

Paper No: PVP2017-65516

DOI: https://doi.org/10.1115/PVP2017-65516

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Topics: Accounting, Design, Engineering design processes, Failure mechanisms, Fatigue, Fukushima nuclear disaster, Japan, 2011, Piping systems, Safety, Seismic analysis, Stress

Proceedings Papers

Earthquake Resistance Assessment of Contaminated Water Storage Tank and its Reinforcement Basic Design at Fukushima

Haruo Morishige, Katsuhisa Fujita, Yousuke Yamashiki

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A053, July 16–20, 2017

Paper No: PVP2017-65677

DOI: https://doi.org/10.1115/PVP2017-65677

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Topics: Design, Earthquake resistant design, Fukushima nuclear disaster, Japan, 2011, Water storage, Earthquakes, Water, Coolants, Concretes, Accidents, Countermeasures

Proceedings Papers

The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature

Kenta Shimomura, Takashi Onizawa, Shoichi Kato, Masanori Ando, Takashi Wakai

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A006, July 16–20, 2017

Paper No: PVP2017-65666

DOI: https://doi.org/10.1115/PVP2017-65666

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Topics: High temperature, Stainless steel, Accidents, Nuclear power stations, Creep, Numerical analysis, Safety, Finite element analysis, Finite element methods, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

Failure Mode Map of Pipes Under Dynamic Loadings

Md Abdullah Al Bari, Ryota Sakemi, Naoto Kasahara

Proc. ASME. PVP2017, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); SPC Track for Senate, V005T11A025, July 16–20, 2017

Paper No: PVP2017-65635

DOI: https://doi.org/10.1115/PVP2017-65635

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Topics: Failure mechanisms, Pipes, Stress, Collapse, Design, Fatigue, Finite element methods, Fukushima nuclear disaster, Japan, 2011, Gravity (Force)

Proceedings Papers

Carbon Fiber Reinforcement of a Water Storage Tank for Beyond Design Basis Loads

Alton Reich, John Charest

Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A024, July 17–21, 2016

Paper No: PVP2016-63062

DOI: https://doi.org/10.1115/PVP2016-63062

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Topics: Carbon fibers, Design, Stress, Water storage, Buckling, Nuclear power stations, Carbon reinforced plastics, Safety, Damage, Earthquakes

Proceedings Papers

Structural Analysis Approach for Risk Assessment Under BDBE

Naoto Kasahara, Izumi Nakamura, Hideo Machida, Koji Okamoto, Takuya Sato

Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A086, July 17–21, 2016

Paper No: PVP2016-63416

DOI: https://doi.org/10.1115/PVP2016-63416

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Topics: Risk assessment, Structural analysis, Failure mechanisms, Failure, Design, Accidents, Creep, Defense industry, Earthquakes, Inelastic analysis

Proceedings Papers

Analytical Study on Failure Mode Map for Lower Formed Head of Reactor Pressure Vessel Under BDBE

Hiroshi Ogawa, Hideo Machida, Naoto Kasahara

Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A087, July 17–21, 2016

Paper No: PVP2016-63487

DOI: https://doi.org/10.1115/PVP2016-63487

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Topics: Failure mechanisms, Reactor vessels, Design, Failure, Earthquakes, Computer simulation, High temperature, Nozzles, Pressure, Stress

Proceedings Papers

Fracture Probability Assessment for Embrittled Reactor Pressure Vessels Under Ultimate Response Guideline Operation

Hsoung-Wei Chou, Chin-Cheng Huang

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A036, July 17–21, 2016

Paper No: PVP2016-63121

DOI: https://doi.org/10.1115/PVP2016-63121

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Topics: Fracture (Materials), Fracture (Process), Probability, Reactor vessels, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Damage, Disasters, Accident management, Accidents

Proceedings Papers

The OECD-NEA Programme on Metallic Component Margins Under High Seismic Loads (MECOS)

Pierre B. Labbé, G. R. Reddy, Cedric Mathon, François Moreau, Spyros A. Karamanos

Proc. ASME. PVP2016, Volume 8: Seismic Engineering, V008T08A017, July 17–21, 2016

Paper No: PVP2016-63119

DOI: https://doi.org/10.1115/PVP2016-63119

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Topics: Accounting, Design, Engineering design processes, Failure mechanisms, Fukushima nuclear disaster, Japan, 2011, Piping systems, Safety, Seismic analysis, Stress

NARROW

Research and Development of Viscous Fluid Dampers for Improvement of Seismic Resistance of Thermal Power Plants: Part 12 Vibration Measurement of Existing Boiler Structure

Dynamic Behavior of a Simplified Cantilever With Progressive Static Loading due to Ratchet Deformation

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing

Modification to Shield Tank Overpressure Protection in a CANDU Reactor for Beyond Design Basis Event

Contribution to Safety Enhancement for BDBE in Structure and Material Fields

Investigation of Fluid Diffusion Properties From Various Flaw Geometries of Piping

Difference of Strength Evaluation Approach Between for DBE and for BDBE

Nuclear Power Plant Fires and Explosions: Part I — Plant Designs and Hydrogen Ignition

Nuclear Power Plant Fires and Explosions: Part II — Hydrogen Ignition Overview

Nuclear Power Plant Fires and Explosions: Part IV — Water Hammer Explosion Mechanisms

The OECD-NEA Programme on Metallic Component Margins Under High Seismic Loads (MECOS): Towards New Criteria

Earthquake Resistance Assessment of Contaminated Water Storage Tank and its Reinforcement Basic Design at Fukushima

The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature

Failure Mode Map of Pipes Under Dynamic Loadings

Carbon Fiber Reinforcement of a Water Storage Tank for Beyond Design Basis Loads

Structural Analysis Approach for Risk Assessment Under BDBE

Analytical Study on Failure Mode Map for Lower Formed Head of Reactor Pressure Vessel Under BDBE

Fracture Probability Assessment for Embrittled Reactor Pressure Vessels Under Ultimate Response Guideline Operation

The OECD-NEA Programme on Metallic Component Margins Under High Seismic Loads (MECOS)

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