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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

Full Structural Weld Overlay on a Super Emergency Feedwater Nozzle at the Dukovany Nuclear Power Plant

Steven L. McCracken, Marek Palán, Pavel Mlynář, Nicholas Mohr

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A092, July 14–19, 2019

Paper No: PVP2019-93664

DOI: https://doi.org/10.1115/PVP2019-93664

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Topics: Emergencies, Feedwater, Nozzles, Nuclear power stations, Overlays (Materials engineering), Maintenance, Metals, ASME Standards, Boilers, Inspection

Proceedings Papers

Consideration of Pressure Vessels Codes and Standards for Fire Emergency Rescue in China: Now and Future

Junjun Wang, Lin Xue, Zhen Ruan, Peiying Wu, Lei Zhang

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A021, July 15–20, 2018

Paper No: PVP2018-84059

DOI: https://doi.org/10.1115/PVP2018-84059

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Topics: China, Emergencies, Engineering standards, Fire, Pressure vessels, Accidents, Leakage, Boilers, Structural elements (Construction)

Proceedings Papers

Measurements of Stress During Thermal Shock in Clad Reactor Pressure Vessel Material Using Time-Resolved In-Situ Synchrotron X-Ray Diffraction

Sam Oliver, Chris Simpson, Andrew James, Christina Reinhard, David Collins, Martyn Pavier, Mahmoud Mostafavi

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A017, July 15–20, 2018

Paper No: PVP2018-84676

DOI: https://doi.org/10.1115/PVP2018-84676

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Topics: Reactor vessels, Stress, Thermal shock, X-ray diffraction, Alloys, Cladding systems (Building), Accidents, Coolants, Cooling, Diamonds

Proceedings Papers

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

Francis H. Ku, Steven L. McCracken

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A082, July 15–20, 2018

Paper No: PVP2018-84981

DOI: https://doi.org/10.1115/PVP2018-84981

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Topics: Feedwater, Metals, Nozzles, Overlays (Materials engineering), Stress analysis (Engineering), Pressurized water reactors, Design, Water, Emergencies, Finite element analysis

Proceedings Papers

A Novel Approach for Assessment of Pressurised Equipment for Slow Depressurisation During Fire

Kaveh Ebrahimi, Saeid Rahimi Mofrad, Barry Millet, Kenneth Kirkpatrick, George Miller

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A035, July 15–20, 2018

Paper No: PVP2018-84236

DOI: https://doi.org/10.1115/PVP2018-84236

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Topics: Fire, American Petroleum Institute, Design, Pressure, Engineers, Finite element analysis, Metals, Temperature, Brittle fracture, Climate

Proceedings Papers

Fracture Mechanical Assessment of VVER Reactor Internals

Vladislav Pištora, Miroslav Švrček, Peter Ferko, Ihor Mirzov

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A016, July 15–20, 2018

Paper No: PVP2018-84589

DOI: https://doi.org/10.1115/PVP2018-84589

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Topics: Fracture (Materials), Emergencies, Temperature, Brittle fracture, Damage, Design, Embrittlement, Fuels, Nuclear power stations, Pipes

Proceedings Papers

Thermo-Mechanical Justification of the FA3 RPV Cover and Bottom Domes Under Normal and Upset, Emergency and Faulted Loading Situations

S. Chapuliot, M. Sportisse, J. Hardouin, S. Vidard

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A072, July 15–20, 2018

Paper No: PVP2018-84553

DOI: https://doi.org/10.1115/PVP2018-84553

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Topics: Domes (Structural elements), Emergencies, Thermomechanics, Carbon, Thermal hydraulics

Proceedings Papers

Research and Development of Viscous Fluid Dampers for Improvement of Seismic Resistance of Thermal Power Plants: Part 4 — Experimental Study on Environmental Applicability and Durability of Damper

Go Tanaka, Keisuke Minagawa, Kiyoshi Aida, Satoshi Fujita

Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A040, July 15–20, 2018

Paper No: PVP2018-84556

DOI: https://doi.org/10.1115/PVP2018-84556

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Topics: Dampers, Durability, Fluids, Industrial research, Thermal power stations, Boilers, Earthquakes, Coal, Shorelines, Combustion

Proceedings Papers

Transient Impact of Valve Closure Times: Disagreements Between Design and Application

Ilker T. Telci, Shesh R. Koirala

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A036, July 16–20, 2017

Paper No: PVP2017-65728

DOI: https://doi.org/10.1115/PVP2017-65728

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Topics: Design, Transients (Dynamics), Valves, Transient analysis, Waves, Actuators, Pressure, Pipes, Surges, Stress

Proceedings Papers

A Method to Estimate Process Plant Seismic Resilience

Antonio C. Caputo, Fabrizio Paolacci

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A023, July 16–20, 2017

Paper No: PVP2017-65464

DOI: https://doi.org/10.1115/PVP2017-65464

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Topics: Resilience, Decision making, Earthquakes, Emergencies, Process industries, Public utilities, Supply chains

Proceedings Papers

An Integration Method for Assessing the Operational Reliability of Underground Gas Storage in Depleted Reservoir

Weichao Yu, Yuan Min, Weihe Huang, Kai Wen, Ye Zhang, Jing Gong

Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A025, July 16–20, 2017

Paper No: PVP2017-65169

DOI: https://doi.org/10.1115/PVP2017-65169

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Topics: Reliability, Reservoirs, Storage, Pipeline systems, Emergencies, Failure, Manufacturing, Natural gas, Natural gas distribution, Reliability theory

Proceedings Papers

Fracture-Mechanics Analysis of the Reactor Pressure Vessel Beznau 1 Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses

Tomas Nicak, Richard Trewin, Elisabeth Keim, Ingo Cremer, Sebastien Blasset, Heinz Hägeli

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A065, July 17–21, 2016

Paper No: PVP2016-63459

DOI: https://doi.org/10.1115/PVP2016-63459

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Topics: Computational fluid dynamics, Fracture mechanics, Reactor vessels, Thermal hydraulics, Stress, Water, Brittleness, Failure, Plumes (Fluid dynamics), Thermal shock

Proceedings Papers

Warm Pre-Stress Tests of the Irradiated RPV Base Material of Beznau Unit 1

Florian Obermeier, Stefan Heußner, Heinz Hägeli, Herbert Schendzielorz, Marco Kaiser, Elisabeth Keim

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A066, July 17–21, 2016

Paper No: PVP2016-63511

DOI: https://doi.org/10.1115/PVP2016-63511

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Topics: Stress, Fracture toughness, Reactor vessels, Temperature, Coolants, Design, Fracture (Materials), Nuclear power stations, Safety, Testing

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

Deterministic and Probabilistic PTS Study for a Reactor Pressure Vessel Considering Plume Cooling Effects

Guian Qian, Markus Niffenegger, Medhat Sharabi, Nathan Lafferty

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A040, July 17–21, 2016

Paper No: PVP2016-63869

DOI: https://doi.org/10.1115/PVP2016-63869

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Topics: Cooling, Plumes (Fluid dynamics), Reactor vessels, Fracture (Materials), Computational fluid dynamics, Transients (Dynamics), Finite element methods, Failure, Nozzles, Probability

Proceedings Papers

Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement

Qingwu Cheng, Harry Adams, Metin Yetisir

Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A004, July 17–21, 2016

Paper No: PVP2016-63855

DOI: https://doi.org/10.1115/PVP2016-63855

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Topics: Emergency core cooling systems, Fibers, Testing, Filtration, Fuels, Nuclear power stations, Regulations, Accidents, Coolants, Cooling

Proceedings Papers

Some Practical Aspects of Class 1E Actuator Qualification on Comparing Test Levels and Design Basis Event Loading

Ronald S. Farrell

Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A003, July 17–21, 2016

Paper No: PVP2016-63526

DOI: https://doi.org/10.1115/PVP2016-63526

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Topics: Actuators, Design, Testing, Safety, Stress, Containment, Nuclear power stations, Valves, Accidents, Cooling

Proceedings Papers

Micro-Porous Coatings and Enhanced CHF for Downward Facing Boiling During Passive Emergency Reactor Cooling

Albert E. Segall, Faruk A. Sohag, Faith R. Beck, Lokanath Mohanta, Fan-Bill Cheung, Timothy J. Eden, John Potter

Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A088, July 17–21, 2016

Paper No: PVP2016-63014

DOI: https://doi.org/10.1115/PVP2016-63014

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Topics: Boiling, Coatings, Critical heat flux, Emergencies, Nuclear reactor cooling, Sprays, Accidents, Vapors, Vessels, Cavities

Proceedings Papers

Design of a Tornado Missile Resistant Shield for the Angra Nuclear Plant

Alton Reich, Jason Moon

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A032, July 19–23, 2015

Paper No: PVP2015-45391

DOI: https://doi.org/10.1115/PVP2015-45391

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Topics: Design, Missiles, Nuclear power stations, Water, Construction, Cooling, Emergencies, Hazards, Risk, Water storage

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NARROW

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

Full Structural Weld Overlay on a Super Emergency Feedwater Nozzle at the Dukovany Nuclear Power Plant

Consideration of Pressure Vessels Codes and Standards for Fire Emergency Rescue in China: Now and Future

Measurements of Stress During Thermal Shock in Clad Reactor Pressure Vessel Material Using Time-Resolved In-Situ Synchrotron X-Ray Diffraction

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

A Novel Approach for Assessment of Pressurised Equipment for Slow Depressurisation During Fire

Fracture Mechanical Assessment of VVER Reactor Internals

Thermo-Mechanical Justification of the FA3 RPV Cover and Bottom Domes Under Normal and Upset, Emergency and Faulted Loading Situations

Research and Development of Viscous Fluid Dampers for Improvement of Seismic Resistance of Thermal Power Plants: Part 4 — Experimental Study on Environmental Applicability and Durability of Damper

Transient Impact of Valve Closure Times: Disagreements Between Design and Application

A Method to Estimate Process Plant Seismic Resilience

An Integration Method for Assessing the Operational Reliability of Underground Gas Storage in Depleted Reservoir

Fracture-Mechanics Analysis of the Reactor Pressure Vessel Beznau 1 Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses

Warm Pre-Stress Tests of the Irradiated RPV Base Material of Beznau Unit 1

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

Deterministic and Probabilistic PTS Study for a Reactor Pressure Vessel Considering Plume Cooling Effects

Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement

Some Practical Aspects of Class 1E Actuator Qualification on Comparing Test Levels and Design Basis Event Loading

Micro-Porous Coatings and Enhanced CHF for Downward Facing Boiling During Passive Emergency Reactor Cooling

Design of a Tornado Missile Resistant Shield for the Angra Nuclear Plant

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