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방인철
Bang, In Cheol

방인철

원자력공학과

  • Nuclear Thermal Hydraulics and Reactor Safety Lab.
  • Website
Research Interests
Nuclear System Design;Nuclear Safety;CHF;Boiling Enhancement technology;Nanofluid;원자력시스템;원자력안전;원자력계통 설계 및 안전해석;나노유체;임계열유속
Lab Description
The lab supports to fill important needs for more thorough treatments of the processes of energy (heat) generation in nuclear processes, the transport of that energy by the reactor coolant to the power cycle, and the limitations imposed by the transport mechanism on the design of nuclear reactor. The research has been focused on the development of enhanced heat transfer technologies in nuclear fission and fusion systems, and the study of fundamental thermal-hydraulic phenomena ultimately related to nuclear safety and economics. The lab is also interested in development of advanced engineered features for nuclear safety systems or safer nuclear reactor based on the innovative ideas. The works are engaged in both experimental and analytical research and development (R&D).
Researcher ID Research Gate ORCiD Scopus Google Scholar
Previous
Experimental investigation of transient behavior in sodium heat pipe system for microreactor File

Jin, Ik Jae , Bang, In Cheol

Article Issue Date2026-06 View0
Numerical Analysis of Heat Pipe Performance Considering Helium Gap Effects File

Celik, Faruk , Bang, In Cheol

Article Issue Date2026-04 View0
Boiling heat transfer characteristics and thermal resistance modeling of corrosion-related unidentified deposit (CRUD) under PWR conditions File

Kim, Ji Yong , Lee, Yunju , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2026-03 View43
A novel self-venting annular wick for heat pipes: Experimental and comparative performance analysis with several wick structures File

Celik, Faruk , Bang, In Cheol

Article Issue Date2026-03 View25
A Comparative Study of Parametric Dynamic Mode Decomposition Algorithms on Thermal-Hydraulics Case Studies File

Riva, Stefano , Missaglia, Andrea , Introini, Carolina , Bang, In Cheol , Cammi, Antonio

Article Issue Date2025-12 View26
Advancing inherent safety in small modular reactors: A CFD-based analysis of the PIUS concept File

Jung, Ju Hun , Bang, In Cheol

Article Issue Date2025-11 View102
Fluid charging effects on thermal performance of sodium heat pipes and new approach for optimal filling File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2025-08 View151
Predicting boiling heat flux, heat transfer coefficient, and regimes Non-intrusively using external acoustics and deep learning File File

Lim, Doyeong , Liu, Yang , Bang, In Cheol

Article Issue Date2025-07 View100
Advanced thermal monitoring in scaled reactors using deep learning-enhanced drone IR imaging File

Lim, Doyeong , Jin, Ik Jae , Bang, In Cheol

Article Issue Date2025-07 View121
Heat pipe type double-containment vessel as passive safety system for small modular reactors File File

Jung, Ju Hun , Kim, Ji Yong , Lee, Dong Hun , Bang, In Cheol

Article Issue Date2025-03 View141
Flow blockage analysis study for liquid metal fast reactor with two different core configurations including normal and inverted core design File

Seo, Joo Hyung , Kim, Ji Yong , Bang, In Cheol

Article Issue Date2024-10 View191
The time for revolutionizing small modular reactors: Cost reduction strategies from innovations in operation and maintenance File

Jin, Ik Jae , Bang, In Cheol

Article Issue Date2024-09 View223
Dry-out limit enhancement strategy in sodium heat pipes: Overfilling effect and modified capillary limit model File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2024-08 View163
Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants File

Park, Ye Yeong , Bang, In Cheol

Article Issue Date2024-07 View165
Operating condition optimization of liquid metal heat pipe using deep learning based genetic algorithm: Heat transfer performance File File

Jin, Ik Jae , Lee, Dong Hun , Bang, In Cheol

Article Issue Date2024-07 View181
Analysis of geyser boiling in liquid metal heat pipe: Impact on startup and shutdown, fuel temperature, and heat removal performance File

Jin, Ik Jae , Bang, In Cheol

Article Issue Date2024-06 View664
Hybrid Heat Pipe Shutdown Rod as a Novel Concept of Passive Safety System for Microreactor File File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2024-06 View176
A novel non-destructive acoustic approach for investigating pool boiling phenomena File

Lim, Do Yeong , Bang, In Cheol

Article Issue Date2024-05 View178
Heat transfer performance prediction for heat pipe using deep learning based on wick type File

Jin, Ik Jae , Park, Ye Yeong , Bang, In Cheol

Article Issue Date2024-03 View197
Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production File File

Kim, Ji Yong , Yoo, Seung Chang , Seo, Joo Hyung , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2024-03 View201
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