معرفی
Seungjin Kim serves as the Capt. James McCarthy, Jr. and Cheryl E. McCarthy Head of Nuclear Engineering and Professor of Nuclear Engineering at Purdue University's College of Engineering. His research focuses on advanced nuclear reactor technologies, thermal-hydraulic systems, and computational fluid dynamics (CFD) modeling. Key areas include two-phase flow phenomena in nuclear systems, reactor safety, and experimental validation of reactor components. He leads efforts in developing testing facilities for fast reactors and innovative irradiation environments.
Kim's work emphasizes experimental and numerical analysis of multiphase flows, particularly in complex geometries like rod bundles and elbows. He has contributed to scaling analysis for sodium cartridge loops and LBE (lead-bismuth eutectic) systems, advancing reactor design and safety. His expertise extends to jet impingement in high-energy piping and interfacial area transport modeling, with applications in reactor core simulation and thermal management.
His research has been published extensively in top-tier journals, covering topics such as pressure drop in wire-wrapped rod bundles, CFD validation for reactor loops, and bubble dynamics in horizontal flows. Collaborations involve developing correlations for reactor core power estimation and improving safety guidelines for high-energy fluid systems.
