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Professor

PROFILE

Adjunct Professor

Nuclear System Engineering

Kim, Sungwoo (김성우)

Current Position

2007 ~ present Senior/Principal Researcher, KAERI
2021 ~ present Team Leader, Corrosion and Water Chemistry Research, KAERI
2025 ~ present Adjunct Professor, Quantum Energy Chemical Engineering, UST

Research Interest

- Corrosion of structural materials in light water reactors and small modular reactors
- Irradiation assisted corrosion of nuclear materials

Education

1996 B.S. Ceramic Engineering, Yonsei University
1998 M.S. Materials Science and Engineering, KAIST
2002 Ph.D. Materials Science and Engineering, KAIST

Work Experience

2002 ~ 2006 Senior Researcher, Battery Research Institute, LG Research Park, LG Chemical Ltd
2007 ~ 2020 Adjunct Professor, Quantum Energy Chemical Engineering, UST

Project

(On-going)
- Advanced technology for repair welding of irradiation-damaged reactor internal component, ’25~30, 17.4B KW (PI)
- Failure analysis of cooling pipes of RCP in Shin-Hanul Unit 2, ’25-27, 300M KW (PI)
(Completed)
- Technology development of verification of materials aging in primary system, ’21~25, 5.2B KW (PI)

Publication

(International Journal)
- Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water, Y.S. Lim, D.J. Kim, S.W. Kim, S.S. Hwang, S.H. Cho, H.P. Kim, Nuclear Engineering and Technology, 57 (2025) 103134
- Stress–strain curve estimation from load–depth curve of spherical indentation test based on finite element analysis and optimization, S. Moon, S. Hong, S.W. Kim, M. Kim, S.G. Lee, Nuclear Engineering and Technology, 57 (2025) 103326
- Stress–strain curve prediction strategy based on instrumented indentation test using master curve of SS316 stress–strain curve, S. Moon, S. Hong, S.W. Kim, M. Kim, S.G. Lee, Nuclear Engineering and Technology, 57 (2025) 103349
- In-situ analysis of SCC initiation on Alloy 600 surface in primary water environment using digital image correlation with electron backscatter diffraction, J.H. Shin, S.W. Kim, D.J. Kim, Nuclear Engineering and Design, 421 (2024) 113095.
- Parametric study on stress distribution of thin disk specimen of rupture disk corrosion test influencing SCC initiation using finite element analysis, T.Y. Kim, S.W. Kim, D.J. Kim, S.T. Kim, Nuclear Engineering and Technology, 56 (2024) 3180-3187.
- Residual stress distribution analysis in a J-groove dissimilar metal welded component of a reactor vessel bottom head using simulation and experiment, D.H. Ahn, J.Y. Lee, M.J. Choi, J.M. Kim, S.W. Kim, W. Woo, Nuclear Engineering and Technology, 56 (2024) 506-519
- Fractography of Stress Corrosion Cracking of 20% Cold Worked Type 304 H Stainless Steel Containing δ-Ferrite in Oxidizing Primary Water, H.P. Kim, J.Y. Lee, S.H. Cho, M.J. Choi, S.W. Kim, H.H. Jin, D.J. Kim, S.S. Hwang, Y.S. Lim, Archives of Metallurgy and Materials, 69 (2024) 49-52
- Effects of Plastic Deformation on Surface Properties and Microstructure of Alloy 690TT Steam Generator Tube, S.H. Jeon, J.Y. Han, S.W. Kim, Transactions of KPVP, 20 (2024)
- Susceptibility of Stress Corrosion Crack Initiation of Type 304 SS in Simulated Primary Water Environment of PWR, S.H. Cho, S.W. Kim, J.Y. Lee, Transactions of KPVP, 20 (2024) 25-31
- Early-Stage M23C6 Morphology at the Phase Boundary in Type 304L Austenitic Stainless Steel Containing δ Ferrite, H.P. Kim, Y.M. Park, H.M. Jang, S.Y. Lim, M.J. Choi, S.W. Kim, D.J. Kim, S.S. Hwang, Y.S. Lim, Metals, 12 (2022) 1794.
- Effects of the dose and depth on the microstructural characteristics of proton-irradiated austenitic 316 stainless steel, Y.S. Lim, D.J. Kim, M.J. Choi, S.S. Hwang, S.W. Kim, Materials Characterization, 194 (2022) 112445.
- New test method for real-time measurement of SCC initiation of thin disk specimen in high-temperature primary water environment, G.W. Jeon, S.W. Kim, D.J. Kim, C.Y. Jeong, Nuclear Engineering and Technology, 54 (2022) 4481.
- Analysis of Dislocation Density in Strain-Hardened Alloy 690 Using Scanning Transmission Electron Microscopy and Its Effect on the PWSCC Growth Behavior, S.W. Kim, T.Y. Ahn, D.J. Kim, Nuclear Engineering and Technology, 53 (2021) 2304.
- Improvement in the Hydrothermal Corrosion Resistance of Ti-based Nitride Coatings by Adding Cr for Accident Tolerant Fuel Cladding Applications, A. Do, D. Kim, H.J. Choi, S.W. Kim, S.Y. Lim, H.G. Lee, W.J. Kim, Journal of Nuclear Materials, 549 (2021) 152903.
- FEA-Based Ultrasonic Focusing Method in Anisotropic Media for Phased Array Systems, S. Moon, T. Kang, S. Han, K.M. Kim, H.H. Jin, S.W. Kim, M. Kim, H. Seo, Applied Sciences, 11 (2021) 8888.
- Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water, Y.S. Lim, D.J. Kim, S.W. Kim, H.P. Kim, Nuclear Engineering and Technology, 51 (2019) 228-237.
- PWSCC growth rate model of alloy 690 for head penetration nozzles of Korean PWRs, S.W. Kim, K.H. Eom, Y.S. Lim, D.J. Kim, Nuclear Engineering and Technology, 51 (2019) 1060-1068.
- Crack growth rate evaluation of alloys 690/152 by numerical simulation of extracted CT specimens, S.H. Lee, S.W. Kim, C.H. Cho, Y.S. Chang, Nuclear Engineering and Technology, 51 (2019) 1805-1815.
- Characterization of internal and intergranular oxidation in Alloy 690 exposed to simulated PWR primary water and its implications with regard to stress corrosion cracking, Y.S. Lim, D.J. Kim, S.W. Kim, S.S. Hwang, H.P. Kim, Materials Characterization, 157 (2019) 109922.
- In-situ investigation of intergranular stress corrosion cracking initiation and coalescence and effects of geometric and microstructural characteristics, D.B. Song, S.W. Kim, S.S. Hwang, D.J. Kim, C.H. Lee, Corrosion, 74 (2018) 1385-1394.
- Effect of Local Strain Distribution of Cold-rolled Alloy 690 on Primary Water Stress Corrosion Crack Growth Behavior, S.W. Kim, T.Y. Ahn, Y.S. Lim, S.S. Hwang, Archives of Metallurgy and Materials, 62 (2017), 1243-1248.
- Intergranular Oxidation of Ni-based Alloy 600 in a Simulated PWR Primary Water Environment, Y.S. Lim, S.W. Kim, S.S. Hwang, H.P. Kim and C.H. Jang, Corrosion Science, 108 (2016) 125-133.
- Residual Stress Assessment of Nickel-based Alloy 690 Welding Parts, S.H. Lee, Y.S. Chang, S.W. Kim, Engineering Failure Analysis, 54 (2015) 57-73.
- Effect of Local Strain Distribution on Stress Corrosion Cracking of Cold-rolled Alloy 690 with Inhomogeneous Microstructure, S.W. Kim, S.S. Hwang, J.M. Lee, CORROSION, 71 (2015) 1071-1081.
- M23C6 Precipitation Behavior and Grain Boundary Serration in Ni-based Alloy 690, Y.S. Lim, D.J. Kim, S.S. Hwang, H.P. Kim, S.W. Kim, Materials Characterization, 96 (2014) 28-39.
- In-situ Monitoring of Micro-scale PWSCC of Ni-based Alloys in a Simulated Primary Water Chemistry of a PWR using an EN-DCPD Technique, S.W. Kim, Y.J. Lee and S.S. Hwang, Current Nanoscience, 10 (2014) 74-77.
- Ex Situ and In Situ Characterization of Stress Corrosion Cracking of Nickel-base Alloys at High Temperature, H.P. Kim, D.J. Kim, S.W. Kim, Y.S. Lim, S.S. Hwang, J. Solid State Electrochemistry, 18 (2014) 309-323.
- Parametric Study on the Tensile Properties of Ni-based Alloy for a VHTR, D.J. Kim, S.J. Jung, B.H. Mun, S.W. Kim, Y.S. Lim, Metallurgical and Materials Transactions A, 45A (2014), DOI: 10.1007/s11661-014-2357-3.
- Role of Grain Boundary Carbides in Cracking Behavior of Ni Base Alloys, S.S. Hwang, Y.S. Lim, S.W. Kim, D.J. Kim and H.P. Kim, Nucl. Eng. Tech., 45 (2013) 73-80.
- Primary Water Stress Corrosion Cracking Analysis in Alloy 600 Steam Generator Nozzle of a Primary Water Reactor, S.S. Hwang, Y.S. Lim, S.W. Kim, Corrosion, 69 (2013) 1051-1059.
- Evaluation of Stress Intensity factor on Axial Crack in CRDM Mock-up Nozzle due to Welding Residual Stress, J.U. Jeong, Y.C. Park, J.B. Choi, Y.S. Chang, S.W. Kim and H.P. Kim, International Journal of Materials and Mechanics Engineering, 1 (2012) 41.
- Evaluation of Galvanic Corrosion Behavior of SA508 Low Alloy Steel and 309L Stainless Steel Cladding of Reactor Pressure Vessel under Simulated Primary Water Environment, S.W. Kim, D.J. Kim and H.P. Kim, Nucl. Eng. Tech., 40 (2012) 773-780.
- In-situ Monitoring of Micro-cracking of Ni-based Alloys at High Temperature Using Electrochemical Noise Technique, S.W. Kim, D.J. Kim and H.P. Kim, Reviews on Advanced Materials Science, 28 (2011) 122-125.
- Effect of Residual Stress of Dissimilar Metal Welding on Stress Corrosion Cracking of Bottom-Mounted Instrumentation Penetration Mock-Up, S.W. Kim, H.P. Kim, J.U. Jeong and Y.S. Chang, Corrosion, 66 (2010) 106001-1-8.
- Electrochemical Noise Analysis of PbSCC of Alloy 600 SG Tube in Caustic Environments at High Temperature, S.W. Kim and H.P. Kim, Corrosion Science, 51 (2009) 191-196.
- Effect of Decarburization Heat Treatment and Chromium Addition on Corrosion Behavior of Carbon Steel, H.S. Shin, S.W. Kim, H.P. Kim and J.K. Park, Corrosion, 65 (2009) 326-331.
- Interpretation of Electrochemical Noise Parameters as Indicators of Initiation and Propagation of SCC of Alloy 600 SG Tube at High Temperature, S.W. Kim and H.P. Kim, Nucl. Eng. Tech., 41 (2009) 1315-1322.
- Thermodynamic and Kinetic Approaches to Lithium Intercalation into Li1+x[Ti5/3Li1/3]O4 Film Electrode, K.N. Jung, S.I. Pyun and S.W. Kim, J. Power Sources, 119 (2003) 637-643.
- Lithium Transport through a Sol-gel Derived Li1-xMn2O4 Film Electrode: Analysis of Current Transient by Monte Carlo Simulation, S.I. Pyun, S.W. Kim and J.M. Ko, J. New Materials for Electrochemical Systems, 5 (2002) 135-141.
- Effect of Pore Size Distribution of Activated Carbon Electrodes on Electric Double-Layer Capacitance Performance, S.I. Pyun, C.H. Kim and S.W. Kim, J. New Materials for Electrochemical Systems, 5 (2002) 289-295.
- Lithium Transport through a Sol-Gel Derived Li1-xMn2O4 Film Electrode : Analyses of Potentiostatic Current Transient and Linear Sweep Voltammogram by Monte Carlo Simulation, S.W. Kim and S.I. Pyun, Electrochim. Acta, 47 (2002) 2843-2855.
- Analysis of Cell Impedance measured on the Li1-xMn2O4 Electrode by PITT and EIS with Monte Carlo Simulation, S.W. Kim and S.I. Pyun, J. Electroanal. Chem. 528 (2002) 114-120.
- Mechanisms of Lithium Transport through Transition Metal Oxides Studied by Analysis of Current Transients, H.C. Shin, S.I. Pyun, S.W. Kim and M.H. Lee, Electrochim. Acta, 46 (2001) 897-906.
- Thermodynamic and Kinetic Approaches to Lithium Intercalation into Li1-xMn2O4 Electrode using Monte Carlo Simulation, S.W. Kim and S.I. Pyun, Electrochim. Acta, 46 (2001) 987-997.
- Lithium Transport through Li1-xMn2O4 Electrode Involving the Ordering of Lithium Ion by Numerical Analysis of Current Transient, S.I. Pyun and S.W. Kim, J. Power Sources, 97-98 (2001) 371-376.
- Thermodynamic Approach to Electrochemical Lithium Intercalation into Li1-xMn2O4 Electrode Prepared by Sol-Gel Method, S.I. Pyun and S.W. Kim, Molecular Crystals and Liquid Crystals, 341 (2000) 155-162.
- Cation Mixing during Lithium Intercalation into and Deintercalation from Li1-xAlyNi1-yO2 (0y0.25) Electrodes, S.I. Pyun, M.H. Lee, H.C. Shin and S.W. Kim, Molecular Crystals and Liquid Crystals, 341 (2000) 163-170.
- Lithium Transport through Li1+x[Ti2-yLiy]O4 (y=0; 1/3) Electrodes by Analysing Current Transients upon Large Potential Steps, S.I. Pyun, S.W. Kim and H.C. Shin, J. Power Sources, 81-82 (1999) 248-254.

(International Conference)

(Patent)

(Book)
- In-situ Monitoring of SCC of Alloy 600 SG Tubing in PWR using EN Analysis, S.-W. Kim, H.-P. Kim, S.-S. Hwang, D.-J. Kim, in Steam Generator Systems, INTECH, 2011.
- Stochastic Approach to Electrochemical Noise Analysis of SCC of Alloy 600 SG Tube in Caustic Environments at High Temperature, S.-W. Kim, H.-P. Kim, in Corrosion Monitoring in Nuclear Systems – Research and Applications, S. Ritter and A. Molander (Ed.), EFC 56, Maney Publishing, 2010.
- SCC of Structural Materials in Primary Water of PWR and Their Integrity, S.-W. Kim, Handbook of Water Chemistries in Nuclear Power Plants, W.-Y. Maeng (Ed.), KAERI (ISBN 978-89-425-1519-6), 2010.
- The Fundamentals and Advances of Solid State Electrochemistry: Intercalation (Insertion) and Deintercalation (Extraction) in Solid State Electrodes, S.-W. Kim, S.-B. Lee, S.-I. Pyun, in Handbook of Solid State Electrochemistry – Fundamentals, Methodology and Recent Advances, Kharton (Ed.), Wiley-VCH, 2009.

Professional Activities

- (2023~present) 한국재료부식학회 교육자격위원회 이사
- (2022~present) 한국압력기기공학회 재료및열과분과 간사

Teaching Experiences

– Corrosion Engineer Expert Education (CSSK, 2023~2026)
– Nuclear Materials Ageing Students Learning Program (KAERI, 2019~2024)

Honors and Awards

– Minister’s Commendation, Ministry of Science and Technology (2022)
– Technical Award, Korean Nuclear Society (2020)
– Early-Career Technology Award, Corrosion Science Society of Korea (2013)

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