Members

2026. 03~Present

Salha is interested in the nuclear reactor safety analysis and developing multi-physics analysis framework.

He is studying the thermal-hydraulic analysis in heat pipe reactors based on experiments and numerical simulations.

2025. 12~Present 

Seoyeon (Our captain) purses to be expert in the reactor safety assessment, especially for two-phase flow and heat transfer.

She is demonstrating the design of double-tube thermosyphon based on experimental works and evaluating the applicability of MARS code for heat pipe/thermosyphon

2025. 12~Present

Hyunhwa is interested in the design of double-tube thermosyphon and heat pipe, which can extend applicability of the passive heat transfer device on advanced reactors.

She is actively conducting CFD analysis on the demonstration of double-tube thermosyphon for design optimization.

2024. 09~Present 

Taeyong is interested in the nuclear reactor safety analysis using MARS code and with application of AI.

He is studying the MARS simulation, especially for the post-CHF heat transfer and MSR.

2024. 11~Present

Seojun is interested in the design of heat pipe microreactor.

He is eager to designing the liquid metal heat pipe (LMHP) experiments to observe the heat transfer performance of LMHP.

2024. 11~Present

Sewook is interested in the improving design of molten salt reactor.

He is designing a novel freeze plug, which can resolve the potential issues of the current/existing designs of the freeze plugs.

2025. 03~Present

Chanyoung is proactively studying the probabilistic neural network as a uncertainty-informative AI tool improving the predictive capability on the thermal-hydraulic phenomena in LWRs and SMRs.

He is also interested in LLM models, which can help the decision making of the operators, in nuclear facilities.

2026. 04~Present

Hyunjun is proactively studying the physics-based/probabalistic neural networks as a tool improving the predictive capability on the thermal-hydraulic phenomena in LWRs and SMRs.

2025. 04~Present

Jongseo is interested in CFD simulation related to the nuclear propulsions such as spacecrafts and submarines.

He is also studying the optimization in fabrication of high-temperature superconducting magnets based on mechanical simulation.

2026. 04~Present

Mijin is highly motivated in reactor safety analysis using MARS-KS code and CFD.

She is assessing and improving the system code capability on post-CHF heat transfer