Yoon-Suk Chang Assistant Professor
- University of Sungkyunkwan
- Computational Fracture Mechanics
- +82 31 201 3323
Ph.D., Sungkyunkwan University, Department of Mechanical Engineering, Korea, 1996.2 M.S., Sungkyunkwan University, Department of Mechanical Engineering, Korea, 1993.2 B.S., Sungkyunkwan University, Department of Mechanical Engineering, Korea, 1991.2
Associate Professor, Kyung Hee University, Korea, 2014 - Present Assistant Professor, Kyung Hee University, Korea, 2010 - 2014 Research Professor, Sungkyunkwan University, Korea, 2004 - 2010 Researcher, University of Tokyo, Japan & University of Stuttgart, Germany, 2002 - 2003 Principal Researcher, Korea Power Engineering Company, Korea, 1996 - 2002 Analyses of technical status/research trend on ultimate pressure capacity of containment, Korea Institute of Nuclear Safety, 2018.04-2022.12 Development of pressure tube flaw evaluation program, Korea Atomic Energy Research Institute, 2017.04-2019.12 Numerical analyses of divertor with plasma facing component, National Research Foundation of Korea, 2017.04-2019.12 High track for storage and management technologies of nuclear spent fuels, Ministry of Trade, Industry and Energy, 2016.06-2021.06 Development of jet loads and dynamic structural integrity evaluation method against high energy line break, Korea Institute of Energy Technology Evaluation and Planning, 2015.09-2018.08 Accomplishment of material property test and development of analysis method for damage evaluation on thermal and irradiation embrittlement in austenitic stainless steel welds of nuclear power plant, Korea Hydro & Nuclear Power Co. Ltd, 2013.09-2018.03 Analyses of technical based on structural integrity evaluation of nuclear components by considering steam explosion, Korea Institute of Nuclear Safety, 2013.07-2018.06
S. H. Kim, Y. S. Chang, D. K. Choi, C. R. Choi, 2018, ”Structural Assessment of Jet Impingement Loads under Postulated Main Steam Line Break Conditions”, Annals of Nuclear Energy, 115: 611-618 S. Y. Je, Y. S. Chang, S. S. Kang, 2017, ”Dynamic Characteristics Assessment of Reactor Vessel Internals with Fluid-structure Interaction“, Nuclear Engineering and Technology, 49(7): 1513-1523 S. H. Kim, Y. S. Chang, Y. J. Cho, 2017, ”Parametric Analyses of Major Nuclear Components and Reinforced Concrete Structures under FCI-induced Explosive Condition“, Nuclear Engineering and Design, 322: 148-158 H. K. Jun, D. W. Kim, I. S. Jeon, S. H. Lee, Y. S. Chang, 2017, ”Investigation of Residual Stresses in a Repair-welded Rail Head considering Solid-state Phase Transformation”, Fatigue and Fracture Engineering Materials and Structures, 40(7): 1059-1071 H. S. Kim, C. K. Oh and Y. S. Chang, 2017, "A New Repair Criterion for SG Tubes with Axial Cracks based on Probabilistic Assessment," Nuclear Engineering and Design, 313: 10-19. S. H. Kim, Y. S. Chang and Y. J. Cho, 2016, "Assessment of Steel Components and Reinforced Concrete Structures under Steam Explosion Conditions," Structural Engineering and Mechanics, 60(2): 337-350. S. J. Lee and Y. S. Chang, 2015, "Evaluation of Crack Growth Rates by using Extended Finite Element Method," Nuclear Engineering and Technology, 47(7): 895-906. D. H. Lim and Y. S. Chang, 2015, "Concept Design Analyses of an ITER Radwaste System Pipeline," Fusion Engineering and Design, 98-99: 2120-2124. S. H. Lee, Y. S. Chang and S. W. Kim, 2015, "Residual Stress Assessment of Nickel-based Alloy 690 Welding Parts," Engineering Failure Analysis, 54: 57-73. S. H. Kim, Y. S. Chang, S. C. Song and Y. J. Cho, 2015, "Assessment of Flooded Reactor Cavity and Penetration Piping," International Journal of Pressure Vessels and Piping, 131: 36-44. T. H. Kim, S. H. Kim and Y. S. Chang, 2015, "Structural Assessment of RPV under Multi-layered Corium Formation Conditions," Nuclear Engineering and Technology, 47(3): 351-361. S. A. Lee, S. H. Lee, Y. S. Chang, 2015, "Evaluation of RPV according to Alternative Fracture Toughness Requirements," Structural Engineering and Mechanics, 53(6): 1271-1286. D. H. Kim, Y. S. Chang and M. J. Jhung, 2014, "Numerical Study on Fluid Flow by Hydrodynamic Loads in RVIs," Structural Engineering and Mechanics, 51(6): 1005-1016. Y. J. Oh and Y. S. Chang, 2014, "Integrated Probabilistic Assessment for DHC Initiation, Growth and LBB of PHWR Pressure Tubes," Nuclear Engineering and Design, 275: 30-43.
C.R. Choi, W.T. Kim, C.R. Choi, Y.S. Chang, 2017, “Impact Test Apparatus at the Time of Pipe Rupture Including a Receiver Tank Capable of Changing the Application to a Pressure Vessel," Korean Intellectual Property Office, PATENT-10-1793218
Grand Prize of Academic Awards, Korean Society of Pressure Vessels and Piping, 2015 Best Teaching Awards in School of Engineering, Kyung Hee University, 2013 Yudam Academic Awards, Korean Society of Mechanical Engineers, 2011 Editorial Board Member, International Journal of Recent Advances in Mechanical Engineering, 2015 – Present Associate Editor, Korean Society of Mechanical Engineers Journal A, 2015 - Present Director of General Affair, Korean Society of Pressure Vessels and Piping, 2015 - 2018 Local Committee Chair, Asian Conference on Experimental Mechanics, 2015 - 2016 Organizing Member / International Board Committee Member, Asia-Pacific Conference on Fracture and Strength, 2011 - Present Steering Committee Member, Asian Society for Integrity of Nuclear Components, 2006 - Present Delegate, ASME Code Committee on Nuclear Inservice Inspection, 2006 - 2010
Computational mechanics, fracture mechanics and damage mechanics: Numerical simulation, structural integrity analysis and probabilistic assessment of major nuclear components based on finite element method, smoothed particle hydrodynamics and molecular dynamics.