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Hyun-Su Kim
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Proceedings Papers

Design of Piping Systems for Accidental Explosion and Fire Events

Necip Onder Akinci, James Loudoun, Krishna Parvathaneni, Hyun-Su Kim
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A028, July 13–15, 2021
Paper No: PVP2021-61650
https://doi.org/10.1115/PVP2021-61650
View Paper titled, Design of Piping Systems for Accidental Explosion and Fire Events
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Topics: Design, Explosions, Failure, Fire, Pipes, Piping design, Resilience
Journal Articles

Plastic Limit Loads for Pipe-in-Pipes With Circumferential Through-Wall Cracks Based on Finite Element Analyses

Se-Chang Kim, Jae-Boong Choi, Hyun-Su Kim, Nam-Su Huh, Kyunghoon Kim
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. June 2018, 140(3): 031202.
Paper No: PVT-17-1259
https://doi.org/10.1115/1.4039846
Published Online: April 25, 2018
View Article titled, Plastic Limit Loads for Pipe-in-Pipes With Circumferential Through-Wall Cracks Based on Finite Element Analyses
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Topics: Fracture (Materials), Pipes, Stress, Finite element analysis, Pressure
Journal Articles

A New Stress Intensification Factor of Pipe-In-Pipes Based on Finite Element Analyses

Se-Chang Kim, Jae-Boong Choi, Moon Ki Kim, Hyun-Su Kim, Nam-Su Huh
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. August 2017, 139(4): 041205.
Paper No: PVT-16-1218
https://doi.org/10.1115/1.4036427
Published Online: April 21, 2017
View Article titled, A New Stress Intensification Factor of Pipe-In-Pipes Based on Finite Element Analyses
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Topics: Breakwaters, Pipes, Stress, Pressure, Finite element analysis
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
https://doi.org/10.1115/PVP2016-63374
View Paper titled, Environmental Fatigue and Fatigue Monitoring System in Korea
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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

Effect of Reverse Bending Method on Pre-Crack Straightness in CTOD Test of Welded Thick Steel Plates

Sehwan Jeong, Hyun-su Kim, Sang-beom Shin, Tae-jong Park
Proc. ASME. IMECE2014, Volume 9: Mechanics of Solids, Structures and Fluids, V009T12A029, November 14–20, 2014
Paper No: IMECE2014-37909
https://doi.org/10.1115/IMECE2014-37909
View Paper titled, Effect of Reverse Bending Method on Pre-Crack Straightness in CTOD Test of Welded Thick Steel Plates
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Topics: Fracture (Materials), Plates (structures), Steel, Stress, Deformation, Compression, Finite element analysis
Proceedings Papers

Structural Integrity Evaluation of High Strength Anchor Bolt for Supporting Steam Generator and Reactor Coolant Pump in Nuclear Power Plants

Eun-Mo Lim, Nam-Su Huh, Hee-Jin Shim, Chang-Kyun Oh, Hyun-Su Kim
Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A008, July 14–18, 2013
Paper No: PVP2013-97612
https://doi.org/10.1115/PVP2013-97612
View Paper titled, Structural Integrity Evaluation of High Strength Anchor Bolt for Supporting Steam Generator and Reactor Coolant Pump in Nuclear Power Plants
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Topics: Anchor bolts, Boilers, Nuclear power stations, Nuclear reactor coolants, Pumps, Stress, Finite element analysis, Fracture mechanics, Surface cracks, Thread
Proceedings Papers

Burst Pressure Evaluation of Axially Flawed Tubes Considering the Effect of Support Plate

Chang Kyun Oh, Hyun Su Kim, Hag Ki Youm, Hong Deok Kim, Han Sub Chung
Proc. ASME. PVP2011, Volume 3: Design and Analysis, 873-876, July 17–21, 2011
Paper No: PVP2011-57489
https://doi.org/10.1115/PVP2011-57489
View Paper titled, Burst Pressure Evaluation of Axially Flawed Tubes Considering the Effect of Support Plate
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Topics: Pressure, Heat exchangers, Plates (structures), Fracture (Materials), Finite element analysis, Petrochemicals, Power stations, Reliability, Safety, Stress
Proceedings Papers

Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure

Han-Beom Seo, Jae-Boong Choi, Young-Jin Kim, Yoon-Suk Chang, Hyun-Su Kim
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 113-118, July 18–22, 2010
Paper No: PVP2010-25604
https://doi.org/10.1115/PVP2010-25604
View Paper titled, Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure
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Topics: Pressure, Surface cracks, Fracture (Materials), Fitness-for-service, Pipes, ASME Standards, Engineering standards, Finite element analysis, Plates (structures), Power stations
Proceedings Papers

A Comparison of Failure Load Assessment Methods for Thin-Walled Tubes With Cracks

Hyun Su Kim, Chang Kyun Oh, Tae Eun Jin
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 697-702, July 26–30, 2009
Paper No: PVP2009-78142
https://doi.org/10.1115/PVP2009-78142
View Paper titled, A Comparison of Failure Load Assessment Methods for Thin-Walled Tubes With Cracks
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Topics: Failure, Fracture (Materials), Stress, Heat exchangers, Failure mechanisms, Finite element analysis, Analytical methods, ASME Standards, Collapse, Inspection
Proceedings Papers

Environmental Fatigue Evaluation of a Korean Nuclear Power Plant

Chang-Kyun Oh, Hyun-Su Kim, Hag-Ki Youm, Tae-Eun Jin, Young-Jin Kim
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 113-119, May 11–15, 2008
Paper No: ICONE16-48346
https://doi.org/10.1115/ICONE16-48346
View Paper titled, Environmental Fatigue Evaluation of a Korean Nuclear Power Plant
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Topics: Fatigue, Nuclear power stations, ASME Standards, Design, Fatigue life, Nozzles, Pipes, Pressure, Reactor vessels, Stress
Proceedings Papers

Assessment of Limit Loads for Circumferential Cracks in Steam Generator Tube Considering Constraining Effect of Tube Support

Hyun Su Kim, Jong Sung Kim, Tae Eun Jin, Hong Deok Kim, Han Sub Chung
Proc. ASME. PVP2005, Volume 3: Design and Analysis, 363-368, July 17–21, 2005
Paper No: PVP2005-71308
https://doi.org/10.1115/PVP2005-71308
View Paper titled, Assessment of Limit Loads for Circumferential Cracks in Steam Generator Tube Considering Constraining Effect of Tube Support
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Topics: Boilers, Fracture (Materials), Stress, Boundary-value problems, Nuclear power stations, Finite element analysis, Heat, Heat exchangers, Nuclear fission, Plates (structures)