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방인철
Bang, In Cheol

방인철

Department of Nuclear Engineering(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
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 View18
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 View20
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 View13
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 View262
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 View24
A novel non-destructive acoustic approach for investigating pool boiling phenomena File

Lim, Do Yeong , Bang, In Cheol

Article Issue Date2024-05 View44
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 View30
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 View23
Carbon neutrality strategy with small modular reactor-based hybrid energy system: A case study for a small Island and isolated power grid File

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

Article Issue Date2024-02 View29
Performance analysis of heat pipe-based passive in-core decay heat removal system for the small modular reactor design with MARS-KS code File

Kim, Ji Yong , Park, Ye Yeong , Bang, In Cheol

Article Issue Date2023-12 View24
Heat-vision based drone surveillance augmented by deep learning for critical industrial monitoring File File

Lim, Do Yeong , Jin, Ik Jae , Bang, In Cheol

Article Issue Date2023-12 View30
Experimental investigation of thermal behavior of overfilled sodium heat pipe File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2023-11 View27
Robust 2D layered MXene matrix-boron carbide hybrid films for neutron radiation shielding File File

Han, Ju-Hyoung , Seok, Shi-Hyun , Jin, Young Ho , Park, Jaeeun , Lee, Yunju , Yeo, Haeng Un , Back, Jong-Ho , Sim, Yeoseon , Chae, Yujin , Wang, Jaewon , et al

Article Issue Date2023-10 View27
OPR1000 원전의 냉매 열수력 종합효과 실험장치 척도설계 File

임도영 , 방인철

Article Issue Date2023-10 View13
The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation File File

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

Article Issue Date2023-09 View25
Experimental investigation of heat transfer limitations in concentric annular sodium heat pipes and thermosyphon File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2023-09 View34
Experimental study on 3D printed heat pipes with hybrid screen-groove combined capillary wick structure File

Park, Ye Yeong , Bang, In Cheol

Article Issue Date2023-09 View31
Effects of decay heat and cooling condition on the reactor pool natural circulation under RVACS operation in a water 2-D slab model File File

Lee, Min Ho , Jerng, Dong Wook , Bang, In Cheol

Article Issue Date2023-05 View36
Development of fault diagnosis for nuclear power plant using deep learning and infrared sensor equipped UAV File

Jin, Ik Jae , Lim, Do Yeong , Bang, In Cheol

Article Issue Date2023-02 View24
Deep-learning-based system-scale diagnosis of a nuclear power plant with multiple infrared cameras File File

Jin, Ik Jae , Lim, Do Yeong , Bang, In Cheol

Article Issue Date2023-02 View31
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