 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

 Professor, Kyung Hee University, Korea, 2019 - Present  Associate Professor, Kyung Hee University, Korea, 2014- 2019  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.