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Jeong, Yong Hoon (정용훈)
교수, Department of Nuclear and Quantum Engineering(원자력및양자공학과)

http://necel.kaist.ac.kr

Research Area
nuclear system design and safety analysis, nuclear hydrogen, desalination, electric vehicle, power transport system
Co-researchers
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    NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
    1
    Depressurization of nuclear power plants through a silica gel-based system

    Kam, Dong Hoon; Jeong, Yong Hoonresearcher; Choi, Sung-Minresearcher; et al, NUCLEAR ENGINEERING AND DESIGN, v.381, pp.1111333, 2021-09

    2
    Mechanistic CHF model development for subcooled flow boiling in a vertical rectangular channel under low pressure

    Song, Jung Hyun; Jung, Jun Yeong; Ch, Soon Heung; et al, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.174, 2021-08

    3
    Investigation of various reactor vessel auxiliary cooling system geometries for a hybrid micro modular reactor

    Lee, Seongmin; Choi, Young Jae; Lee, Jeong-Ikresearcher; et al, NUCLEAR ENGINEERING AND DESIGN, v.379, 2021-08

    4
    Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

    Khasawneh, Khalid; Jeong, Yong Hoonresearcher, NUCLEAR ENGINEERING AND DESIGN, v.378, 2021-07

    5
    Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle

    Choi, Yu Jung; Kam, Dong Hoon; Papadopoulos, Petros; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.6, pp.1756 - 1768, 2021-06

    6
    CHF on Anodized Zirconium-based Alloy Surfaces with Protective Oxide Layers for ATF cladding

    Kam, Dong Hoon; Yu, Hyoung Suk; Jeong, Yong Hoonresearcher; et al, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.170, 2021-05

    7
    Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors

    Amidu, Muritala Alade; Addad, Yacine; Lee, Jeong-Ikresearcher; et al, NUCLEAR ENGINEERING AND DESIGN, v.376, 2021-05

    8
    An investigation of pressure build-up effects due to check valve's closing characteristics using dynamic mesh techniques of CFD

    Kim, Nam-Seok; Jeong, Yong-Hoonresearcher, ANNALS OF NUCLEAR ENERGY, v.152, pp.107996, 2021-03

    9
    Feasibility study of solar-nuclear hybrid system for distributed power source

    Son, In-Woo; Jeong, Yong Hoonresearcher; Choi, Young Jae; et al, ENERGY CONVERSION AND MANAGEMENT, v.230, pp.113808, 2021-02

    10
    Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe

    Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; et al, NUCLEAR ENGINEERING AND DESIGN, v.370, 2020-12

    11
    Correction factor development for the 2006 Groeneveld CHF look-up table for rectangular channels under low pressure

    Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; et al, NUCLEAR ENGINEERING AND DESIGN, v.370, pp.110869, 2020-12

    12
    Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code

    Kim, Mun Soo; Jeong, Yong Hoonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.12, pp.2743 - 2759, 2020-12

    13
    The importance of representative aerosol diameter and bubble size distribution in pool scrubbing

    Kim, Yo Han; Kam, Dong Hoon; Yoon, Jongwoong; et al, ANNALS OF NUCLEAR ENERGY, v.147, 2020-11

    14
    An experimental observation of the effects of submicron- and micron-sized mesoporous silica particles on the critical heat flux

    Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.160, pp.120182, 2020-10

    15
    A novel approach for critical heat flux enhancement during severe accident mitigation with removal of radioactive materials from the coolant

    Kam, Dong Hoon; Jeong, Yong Hoonresearcher; Choi, Sung-Minresearcher; et al, NUCLEAR ENGINEERING AND DESIGN, v.365, pp.110715 - 110725, 2020-08

    16
    Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident

    Lee, Seongmin; Jeong, Yong Hoonresearcher, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.6, pp.1110 - 1119, 2020-06

    17
    Flow boiling CHF experiment with sudden expansion tubes

    Kim, Yong Jin; Song, Sub Lee; Moon, Sang-Ki; et al, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.114, 2020-05

    18
    Design Of Air-Cooled Waste Heat Removal System With String Type Direct Contact Heat Exchanger And Investigation Of Oil Film Instability

    Moon, Jangsik; Jeong, Yong Hoonresearcher; Addad, Yacine, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.4, pp.734 - 741, 2020-04

    19
    Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials

    Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, ANNALS OF NUCLEAR ENERGY, v.136, 2020-02

    20
    A heat transfer model development for CHF prediction with consideration of dry patch characteristics

    Kam, Dong Hoon; Jeong, Yong Hoonresearcher; No, Hee Cheonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.148, 2020-02
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