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eBook Chapter

Assessment of Fretting-Wear Damage in Nuclear and Process Equipment

Publisher: ASME-Wiley
Published: 2022
ISBN: 9781119810964
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Topics: Damage, Wear
Journal Articles

Fuel Assembly Concept of the Canadian Supercritical Water-Cooled Reactor

Metin Yetisir, Holly Hamilton, Rui Xu, Michel Gaudet, David Rhodes, Mitch King, Kittmer Andrew, Ben Benson
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011010.
Paper No: NERS-17-1035
DOI: https://doi.org/10.1115/1.4037818
Published Online: December 4, 2017
View Article titled, Fuel Assembly Concept of the Canadian Supercritical Water-Cooled Reactor
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Topics: Fuels, Manufacturing, Water, Pressure
Proceedings Papers

Fretting-Wear Damage due to Vibration in Nuclear and Process Equipment

Michel J. Pettigrew, Metin Yetisir, Nigel J. Fisher, Bruce A. W. Smith, Colette E. Taylor, Victor P. Janzen
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A032, July 16–20, 2017
Paper No: PVP2017-65272
DOI: https://doi.org/10.1115/PVP2017-65272
View Paper titled, Fretting-Wear Damage due to Vibration in Nuclear and Process Equipment
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Topics: Damage, Vibration, Wear, Fuel rods, Fuels, Heat exchangers, Pipes, Piping systems
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
View Paper titled, Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement
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Topics: Emergency core cooling systems, Fibers, Testing, Filtration, Fuels, Nuclear power stations, Regulations, Accidents, Coolants, Cooling
Journal Articles

Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core

Metin Yetisir, Rui Xu, Michel Gaudet, Mohammad Movassat, Holly Hamilton, Mohammedhossein Nimrouzi, John A. Goldak
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011007.
Paper No: NERS-15-1093
DOI: https://doi.org/10.1115/1.4031247
Published Online: December 9, 2015
View Article titled, Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core
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Topics: Fuels, Pressure, Supercritical water reactors, Temperature, Flow (Dynamics), Water, Design, Coolants, Cladding systems (Building), Manufacturing
Proceedings Papers

A Methodology for Optimizing Startup-Shutdown Transients for Pressure Vessel Integrity

Hossein Nimrouzi, John A. Goldak, Metin Yetisir
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A049, July 19–23, 2015
Paper No: PVP2015-45975
DOI: https://doi.org/10.1115/PVP2015-45975
View Paper titled, A Methodology for Optimizing Startup-Shutdown Transients for Pressure Vessel Integrity
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Topics: Pressure vessels, Transients (Dynamics), Design, Cycles, Pressure, Temperature, Computer software, Geometry, Mesh generation, Optimization
Proceedings Papers

The Role of Computational Weld Mechanics in the Weld Repair of Canada’s NRU Nuclear Reactor

John A. Goldak, Metin Yetisir, Rob Pistor
Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A104, July 14–18, 2013
Paper No: PVP2013-97948
DOI: https://doi.org/10.1115/PVP2013-97948
View Paper titled, The Role of Computational Weld Mechanics in the Weld Repair of Canada’s NRU Nuclear Reactor
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Topics: Maintenance, Nuclear reactors, Aluminum, Welding, Biomedicine, Design, Aluminum plate, Cancer, Chalk, Computers
Proceedings Papers

Residual Stress Distributions and Guidelines for Crack Inspection in Pipe Bends

Metin Yetisir, Zane Walker
Proc. ASME. PVP2012, Volume 7: Operations, Applications and Components, 35-46, July 15–19, 2012
Paper No: PVP2012-78507
DOI: https://doi.org/10.1115/PVP2012-78507
View Paper titled, Residual Stress Distributions and Guidelines for Crack Inspection in Pipe Bends
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Topics: Fracture (Materials), Inspection, Pipe bends, Stress, Cracking (Materials), Failure, Fracture (Process), Manufacturing, Nuclear power stations, Pipes
Proceedings Papers

Thermal Fatigue in CANDU Stations

Metin Yetisir
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 589-596, July 12–16, 2009
Paper No: ICONE17-75603
DOI: https://doi.org/10.1115/ICONE17-75603
View Paper titled, Thermal Fatigue in CANDU Stations
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Topics: Fatigue, Design, Boiling water reactors, Pressurized water reactors, Thermal stratification, Failure, Fluids, Heavy water reactors, Nuclear industry, Oscillations
Proceedings Papers

A Simple Energy Approach to Assess Vibration and Fretting-Wear Damage in Process Equipment

Michel J. Pettigrew, Metin Yetisir, Nigel J. Fisher, Colette E. Taylor, Bruce A. W. Smith
Proc. ASME. PVP2007, Volume 4: Fluid-Structure Interaction, 281-287, July 22–26, 2007
Paper No: PVP2007-26082
DOI: https://doi.org/10.1115/PVP2007-26082
View Paper titled, A Simple Energy Approach to Assess Vibration and Fretting-Wear Damage in Process Equipment
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Topics: Damage, Vibration, Wear, Heat exchangers, Nuclear fuels, Condensers (steam plant), Damping, Finite element analysis, Flow-induced vibrations, Mode shapes