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Kim, Ji Hyun (김지현)

Department
School of Mechanical, Aerospace and Nuclear Engineering(기계항공및원자력공학부)
Research Interests
High temperature water corrosion, Liquid metal corrosion, Material degradation simulation
Lab
UNIST Nuclear Innovative Materials Laboratory(UNIMAT)
Website
http://unimat.unist.ac.kr/
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Issue DateTitleAuthor(s)TypeViewAltmetrics
201901Initial oxidation behavior of Fe-Cr-Si alloys in 1200 degrees C steamMoon, Joonho; Kim, Sungyu; Park, Won Dong, et alARTICLE10 Initial oxidation behavior of Fe-Cr-Si alloys in 1200 degrees C steam
201812Meso-scale multi-physics full coupling within porous CRUD deposits on nuclear fuelPark, Byung Gi; Seo, Seungjin; Kim, Sung Joong, et alARTICLE17 Meso-scale multi-physics full coupling within porous CRUD deposits on nuclear fuel
201810Fatigue behavior of AISI 8620 steel exposed to magnetic fieldChoi, Kyoung Joon; Yoo, Seung Chang; Ham, Junhyuk, et alARTICLE21 Fatigue behavior of AISI 8620 steel exposed to magnetic field
201810Natural circulation characteristics under various conditions on heavy liquid metal test loopRyu, Kyung Ha; Ban, Byoung Min; Lee, Tae Hyun, et alARTICLE282 Natural circulation characteristics under various conditions on heavy liquid metal test loop
201806Survivability assessment of Viton in safety-related equipment under simulated severe accident environmentsRyu, Kyungha; Song, Inyoung; Lee, Taehyun, et alARTICLE43 Survivability assessment of Viton in safety-related equipment under simulated severe accident environments
201804Microscopic characterization of pretransition oxide formed on Zr-Nb-Sn alloy under various Zn and dissolved hydrogen concentrationsKim, Sungyu; Kim, Taeho; Kim, Ji Hyun, et alARTICLE195 Microscopic characterization of pretransition oxide formed on Zr-Nb-Sn alloy under various Zn and dissolved hydrogen concentrations
201802Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditionsKim, Taeho; Choi, Kyoung Joon; Yoo, Seung Chang, et alARTICLE100 Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions
201802Statistical analysis of parameter estimation of a probabilistic crack initiation model for Alloy 182 weld considering right-censored data and the covariate effectPark, Jae Phil; Park, Chanseok; Oh, Young-Jin, et alARTICLE51 Statistical analysis of parameter estimation of a probabilistic crack initiation model for Alloy 182 weld considering right-censored data and the covariate effect
201801Formation of 3D graphene-Ni foam heterostructures with enhanced performance and durability for bipolar plates in a polymer electrolyte membrane fuel cellSim, Yeoseon; Kwak, Jinsung; Kim, Se-Yang, et alARTICLE275 Formation of 3D graphene-Ni foam heterostructures with enhanced performance and durability for bipolar plates in a polymer electrolyte membrane fuel cell
201712다중금속복합층 핵연료 피복관의 필거링 공정에 관한 유한 요소 해석 연구김태용; 이정현; 김지현ARTICLE258 다중금속복합층 핵연료 피복관의 필거링 공정에 관한 유한 요소 해석 연구
201711Reply to discussion on “Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy” by S.C. Yoo, K.J. Choi, T. Kim, S.H. Kim, J.Y. Kim, J.H. Kim [Corros. Sci. 111 (2016) 39]Yoo, Seung Chang; Choi, Kyoung Joon; Kim, Taeho, et alARTICLE196 Reply to discussion on “Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy” by S.C. Yoo, K.J. Choi, T. Kim, S.H. Kim, J.Y. Kim, J.H. Kim [Corros. Sci. 111 (2016) 39]
201710Zinc Adsorption and Hydration Structures at Yttria-Stabilized Zirconia SurfacesHou, Binyang; Kim, Taeho; Kim, Seunghyun, et alARTICLE100 Zinc Adsorption and Hydration Structures at Yttria-Stabilized Zirconia Surfaces
201705In situ investigation of the oxidation of Zr-Nb-Cu alloy in high-temperature hydrogenated waterKim, Taeho; Kim, Seunghyun; Lee, Chung-yong, et alARTICLE240 In situ investigation of the oxidation of Zr-Nb-Cu alloy in high-temperature hydrogenated water
201703Effect of defects on reaction of NiO surface with Pb-contained solutionKim, Jongjin; Hou, Binyang; Park, Changyong, et alARTICLE224 Effect of defects on reaction of NiO surface with Pb-contained solution
201703Enhancement of corrosion resistance in carbon steels using nickel-phosphorous/titanium dioxide nanocomposite coatings under high-temperature flowing waterKim, Seunghyun; Kim, Jeong Won; Kim, Ji HyunARTICLE455 Enhancement of corrosion resistance in carbon steels using nickel-phosphorous/titanium dioxide nanocomposite coatings under high-temperature flowing water
201612Orientation-Dependent Hydration Structures at Yttria-Stabilized Cubic Zirconia SurfacesHou, Binyang; Kim, Seunghyun; Kim, Taeho, et alARTICLE186 Orientation-Dependent Hydration Structures at Yttria-Stabilized Cubic Zirconia Surfaces
201611Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactorsChoi, Sang Il; Lee, Gyeong-Geun; Kwon, Junhyun, et alARTICLE191 Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors
201611Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodiumShin, Sang Hun; Lee, Jeonghyeon; Kim, Jun Hwan, et alARTICLE273 Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodium
201610Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloyYoo, Seung Chang; Choi, Kyoung Joon; Kim, Taeho, et alARTICLE489 Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy
201610Effects of thermal aging and stress triaxiality on PWSCC initiation susceptibility of nickel-based Alloy 600Yoo, Seung Chang; Choi, Kyoung Joon; Kim, Taeho, et alARTICLE262 Effects of thermal aging and stress triaxiality on PWSCC initiation susceptibility of nickel-based Alloy 600

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