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Proceedings Papers

Elastic Follow-Up Factor for Cruciform Plate Under Bi-Axial Loading

Kuk-Hee Lee, Yun-Jae Kim, Robert A. Ainsworth, David Dean, Tae-Eun Jin
Proc. ASME. PVP2011, Volume 3: Design and Analysis, 479-485, July 17–21, 2011
Paper No: PVP2011-57185
https://doi.org/10.1115/PVP2011-57185
View Paper titled, Elastic Follow-Up Factor for Cruciform Plate Under Bi-Axial Loading
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Topics: Creep, Finite element analysis, Geometry, Plates (structures), Poisson ratio, Stress
Proceedings Papers

Comparison of Plastic Loads for Elbows With Experimental Data

Jae-Jun Han, Kuk-Hee Lee, Yun-Jae Kim, Peter J. Budden, Tae-Eun Jin
Proc. ASME. PVP2011, Volume 3: Design and Analysis, 863-871, July 17–21, 2011
Paper No: PVP2011-57486
https://doi.org/10.1115/PVP2011-57486
View Paper titled, Comparison of Plastic Loads for Elbows With Experimental Data
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Topics: Stress, ASME Boiler and Pressure Vessel Code, Finite element analysis, Plastics
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

Development of Engineering Formula for Welding Residual Stress Distributions of Dissimilar Welds on Nozzle in Nuclear Component

Jong-Sung Kim, Tae-Eun Jin
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 1027-1032, July 22–26, 2007
Paper No: PVP2007-26729
https://doi.org/10.1115/PVP2007-26729
View Paper titled, Development of Engineering Formula for Welding Residual Stress Distributions of Dissimilar Welds on Nozzle in Nuclear Component
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Topics: Nozzles, Stress, Welded joints, Welding, Finite element analysis, American Petroleum Institute, Drilling, Residual stresses
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

A Study on the Hydrogen Embrittlement Mitigation of Carbon and Low Alloy Steel for Nuclear Power Plant Piping

Jin-Seok Park, Jong-Sung Kim, Jung-Gu Kim, Tae-Eun Jin
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 127-132, April 25–29, 2004
Paper No: ICONE12-49368
https://doi.org/10.1115/ICONE12-49368
View Paper titled, A Study on the Hydrogen Embrittlement Mitigation of Carbon and Low Alloy Steel for Nuclear Power Plant Piping
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Topics: Alloy steel, Carbon, Electrodiffusion, Hydrogen embrittlement, Nuclear power stations, Pipes
Proceedings Papers

Fatigue Evaluation of RCS Branch Line for License Renewal Application

Il-Kwun Nam, Hagki Youm, Tae Eun Jin, Byung Sup Kim
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 169-174, July 17–20, 2006
Paper No: ICONE14-89355
https://doi.org/10.1115/ICONE14-89355
View Paper titled, Fatigue Evaluation of RCS Branch Line for License Renewal Application
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Topics: Fatigue, Licensing, Thermal stratification, Nuclear power stations, Computational fluid dynamics, Fatigue analysis, Finite element analysis, Pipes, Safety, Stress
Proceedings Papers

Fracture Mechanics Evaluation Considering Thermal Aging Embrittlement

Yoon-Suk Chang, Tae-Eun Jin
Proc. ASME. PVP2002, Fatigue, Fracture and Damage Analysis, Volume 2, 119-124, August 5–9, 2002
Paper No: PVP2002-1359
https://doi.org/10.1115/PVP2002-1359
View Paper titled, Fracture Mechanics Evaluation Considering Thermal Aging Embrittlement
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Topics: Embrittlement, Fracture mechanics, Coolants, Evaluation methods, Failure, Ferrites (Magnetic materials), Fracture toughness, Materials properties, Operating temperature, Pipes
Proceedings Papers

Evaluation of Microstructure and Residual Stress on Bi-Material Welded Part

Jong-Sung Kim, Seung-Gun Lee, Tae-Eun Jin
Proc. ASME. PVP2002, Computational Weld Mechanics, Constraint, and Weld Fracture, 27-32, August 5–9, 2002
Paper No: PVP2002-1102
https://doi.org/10.1115/PVP2002-1102
View Paper titled, Evaluation of Microstructure and Residual Stress on Bi-Material Welded Part
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Topics: Stress, Nuclear power stations, Welded joints, Welding, Diffusion (Physics), Finite element methods, Heat treating (Metalworking), Thermodynamics
Proceedings Papers

Effect of Plasticity on Fatigue Life of Welded Nuclear Component With Local Brittle Zone

Jong-Sung Kim, Se-Hwan Lee, Tae-Eun Jin
Proc. ASME. PVP2003, Residual Stress, Fitness-For-Service, and Manufacturing Processes, 59-64, July 20–24, 2003
Paper No: PVP2003-2047
https://doi.org/10.1115/PVP2003-2047
View Paper titled, Effect of Plasticity on Fatigue Life of Welded Nuclear Component With Local Brittle Zone
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Topics: Brittleness, Fatigue life, Plasticity, Tensile strength, Fatigue, Welded joints, Alloy steel, Base metals, Deformation, Fatigue analysis
Proceedings Papers

A Study on Fatigue Analysis Procedure of Nuclear Welded Structures Based on Structural Stress and Fracture Mechanics Approach

Jong-Sung Kim, Tae-Eun Jin
Proc. ASME. PVP2004, Residual Stress, Fracture, and Stress Corrosion Cracking, 49-55, July 25–29, 2004
Paper No: PVP2004-2647
https://doi.org/10.1115/PVP2004-2647
View Paper titled, A Study on Fatigue Analysis Procedure of Nuclear Welded Structures Based on Structural Stress and Fracture Mechanics Approach
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Topics: Fatigue analysis, Fracture mechanics, Stress, Fatigue cracks, Cycles, Fatigue testing, Finite element model, Shear (Mechanics), Welded joints
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)
Proceedings Papers

Development and Application of a Plugging Margin Evaluation Method Taking Into Account the Fouling of Shell-and-Tube Heat Exchangers

Kyeong Mo Hwang, Tae Eun Jin
Proc. ASME. PVP2005, Volume 7: Operations, Applications, and Components, 175-180, July 17–21, 2005
Paper No: PVP2005-71289
https://doi.org/10.1115/PVP2005-71289
View Paper titled, Development and Application of a Plugging Margin Evaluation Method Taking Into Account the Fouling of Shell-and-Tube Heat Exchangers
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Topics: Evaluation methods, Heat exchangers, Shells, Nuclear power stations, Cooling, Design, Flow (Dynamics), Heat transfer, Heat transfer coefficients, Thermal efficiency