معرفی
Dr. Taeho Kim serves as an Assistant Scientist in the Department of Nuclear Engineering and Engineering Physics within the College of Engineering at the University of Wisconsin-Madison. His research laboratory is located in Room 813 of the Engineering Research Building at 1500 Engineering Drive, Madison, WI 53706.
His primary research investigates corrosion characteristics of nuclear reactor materials, specifically zirconium fuel cladding and structural components (including nickel-based alloys and stainless steels) in pressurized water reactors. He employs advanced analytical methodologies such as in-situ Raman spectroscopy, electrochemical impedance spectroscopy, transmission electron microscopy (TEM), scanning electron microscopy (SEM), synchrotron X-ray absorption spectroscopy, and X-ray reflectivity to characterize oxide film properties. Current work focuses on ultraviolet radiation effects on zirconium alloy corrosion behavior under simulated reactor conditions.
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