Researcher Page

사진
Jeong, Yong Hoon (정용훈)
교수, (원자력및양자공학과)
Research Area
nuclear system design and safety analysis, nuclear hydrogen, desalination, electric vehicle, power transport system
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    NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
    1
    Combined effect of a corrodible material and acidic fluid on flow boiling crisis

    Jung, Jun Yeong; Lee, Min Suk; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.143, 2023-04

    2
    Simulation of high temperature fuel rod bundle behavior during the QUENCH-06 experiment using CINEMA code

    Jeong, Woonho; Son, Donggun; Park, Jaehwan; et al, ANNALS OF NUCLEAR ENERGY, v.182, 2023-03

    3
    Preliminary study on a new self-sealing strategy for nuclear reactor containment buildings using phase change materials

    Choi, Yonadan; Jung, Jun Yeong; Lee, Min Suk; et al, NUCLEAR ENGINEERING AND DESIGN, v.402, 2023-02

    4
    Improvement of the subcooled boiling model using a new net vapor generation correlation inferred from artificial neural networks to predict the void fraction profiles in the vertical channel

    Lee, Taebeom; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.12, pp.4776 - 4797, 2022-12

    5
    A study of the behavior of the floating absorber for safety at transient(FAST) in an innovative sodium-cooled fast reactor (iSFR)

    Lee, Seongmin; Kim, Yonghee; Choi, Yonadan; et al, ANNALS OF NUCLEAR ENERGY, v.179, 2022-12

    6
    Analysis on Fire-Retardant Performance of non-Class 1E Cables Depending on the Ambient Temperature Condition Surrounding the Facilities for Flame Test of Cables

    Moon, Youngseob; Jeong, Yonghoon, NUCLEAR TECHNOLOGY, v.208, no.9, pp.1393 - 1405, 2022-09

    7
    Experimental evaluations of the critical heat flux in terms of the heater dimensions, orientation, and surface morphology

    Lee, Min Suk; Jung, Jun Yeong; Kam, Dong Hoon; et al, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.136, 2022-07

    8
    Modeling of droplet diameter changes during reflood into RELAP5/Mod3.3

    Park, Ju Hyun; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.393, 2022-07

    9
    Inherent safety enhancement by design optimization of a floating absorber for safety at transient (FAST) in an advanced burner reactor

    Lee, Seongmin; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.172, 2022-07

    10
    Role and Collaboration of Radiation Protection Experts: Summary of Discussions between the Japan Health Physics Society and the Korean Association of Radiation Protection Related to Tritiated Water

    Sasaki, Michiya; Yoshida, Hiroko; Kai, Michiaki; et al, JOURNAL OF RADIATION PROTECTION AND RESEARCH, v.47, no.2, pp.107 - 109, 2022-06

    11
    Observation of the jet transition at a single vertical nozzle under pool scrubbing conditions

    Yoon, Jongwoong; Kim, Yo Han; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.171, 2022-06

    12
    Flow boiling experiments for CHF evaluation under downward-facing heating including flow visualization: Effects of pressure, orientation, mass flux, and local quality

    Jung, Jun Yeong; Lee, Min Suk; Park, Hae Min; et al, ANNALS OF NUCLEAR ENERGY, v.171, 2022-06

    13
    Experimental study of the nozzle size effect on aerosol removal by pool scrubbing

    Kim, Yo Han; Yoon, Jongwoon; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.385, 2021-12

    14
    Magnetic withdrawal of particles for multiple purposes in nuclear power plants

    Kam, Dong Hoon; Jeong, Yong Hoon; Choi, Sung-Min; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.12, pp.3979 - 3989, 2021-12

    15
    Depressurization of nuclear power plants through a silica gel-based system

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

    16
    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

    17
    Investigation of various reactor vessel auxiliary cooling system geometries for a hybrid micro modular reactor

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

    18
    Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

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

    19
    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

    20
    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-Ik; et al, NUCLEAR ENGINEERING AND DESIGN, v.376, 2021-05

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