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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
A novel non-destructive acoustic approach for investigating pool boiling phenomena File

Lim, Do Yeong , Bang, In Cheol

Article Issue Date2024-05 View17
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 View13
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 View15
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 View10
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 View13
Experimental investigation of thermal behavior of overfilled sodium heat pipe File

Lee, Dong Hun , Bang, In Cheol

Article Issue Date2023-11 View6
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 View10
OPR1000 원전의 냉매 열수력 종합효과 실험장치 척도설계 File

임도영 , 방인철

Article Issue Date2023-10 View4
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 View10
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 View14
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 View11
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 View11
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 View11
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 View7
Application of two different similarity laws for the RVACS design File File

Lee, Min Ho , Hwang, Ji Hwan , Choi, Ki Hyun , Jerng, Dong Wook , Bang, In Cheol

Article Issue Date2022-12 View3
파울링된 피복관 표면의 가압 경수로 운전환경에서의 미포화 비등 열전달 성능평가를 위한 실험장치 구축 연구 File

김지용 , 이윤주 , 함준혁 , 김지현 , 방인철

Article Issue Date2022-10 View13
Study on blockage after downward discharge of the molten metallic fuel with radiographic visualization File File

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

Article Issue Date2022-01 View3
Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system File

Seo, Seok Bin , Bang, In Cheol , Ninokata, Hisashi , Cammi, Antonio

Article Issue Date2021-09 View13
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform File

Kim, Kyung Mo , Bang, In Cheol

Article Issue Date2021-03 View2
Effective energy management design of spent fuel dry storage based on hybrid controlrod-heatpipe File

Kim, Kyung Mo , Bang, In Cheol

Article Issue Date2021-02 View6
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