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Heepyo Hong

Seoul National University

Kwanak-gu

Seoul, 151-742

Korea, Republic of (South Korea)

SCHOLARLY PAPERS

9

DOWNLOADS

377

TOTAL CITATIONS

3

Scholarly Papers (9)

1.

Experimental Study on Flow Boiling Chf in Annulus Channel Under Heaving Conditions Using Simulant Fluid R134a Targeting Nuclear Reactor Applications

Number of pages: 22 Posted: 16 Aug 2023
Seoul National University, Seoul National University, Seoul National University, Seoul National University, Seoul National University, Korea Institute of Nuclear Safety, Seoul National University and Seoul National University
Downloads 52 (1,063,489)

Abstract:

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critical heat flux, heaving motion, flow boiling, heater rod, floating nuclear power plant, offshore nuclear reactor

2.

Experimental Investigation of Helical Fin and Inclination Effect on Critical Heat Flux

Number of pages: 37 Posted: 16 May 2023
Seoul National University, Seoul National University, Seoul National University, Seoul National University, Seoul National University, Korea Institute of Nuclear Safety, Seoul National University and Seoul National University
Downloads 49 (1,074,648)

Abstract:

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critical heat flux, Helical-finned heater, Inclination, Simulant fluid, Marine reactor

3.

Wall Heat Partitioning Model with Bubble Tracking Method for Nucleate Boiling Considering Conjugate Heat Transfer Coupled with Openfoam

Number of pages: 30 Posted: 27 May 2024
Seoul National University, Seoul National University, Korea Institute of Nuclear Safety and Seoul National University
Downloads 48 (1,097,529)

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Heat partitioning, Bubble tracking, Boiling heat transfer, Conjugate heat transfer, Pool boiling

4.

Critical Heat Flux Correlations for Tube and Annulus Geometries Under Inclination and Rolling Conditions

Number of pages: 36 Posted: 05 Nov 2022
Korea Institute of Nuclear Safety, Seoul National University, Seoul National University, Seoul National University, Seoul National University and Seoul National University
Downloads 48 (1,086,013)

Abstract:

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Critical heat flux, Correlation, Inclination, Rolling, Annuli, Tubes

5.

Experimental Study on Flow Boiling Chf of a Helical Finned Rod Under Heaving Conditions Using Simulant Fluid R134a

Number of pages: 27 Posted: 09 Jan 2024
Seoul National University, Korea Atomic Energy Research Institute, Seoul National University, Seoul National University, Seoul National University, Seoul National University, Korea Institute of Nuclear Safety, Seoul National University and Seoul National University
Downloads 47 (1,121,190)

Abstract:

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Critical heat flux, heaving motion, helical finned rod, floating nuclear power plant, offshore nuclear reactor

6.

Boiling Heat Flux Partitioning Model with Bubble Tracking Method Considering Bubble Merger and Stochastic Characteristics

Number of pages: 37 Posted: 03 Nov 2023
Seoul National University, Seoul National University, Korea Institute of Nuclear Safety and Seoul National University
Downloads 44 (1,145,425)
Citation 3

Abstract:

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Heat partitioning, Bubble tracking, Boiling heat transfer, Simulation, Pool boiling

7.

Development of Flow Boiling Critical Heat Flux Correlations Under Heaving Motions Based on Decomposition of Additional Force and Periodic Motion Effects

Number of pages: 62 Posted: 17 Feb 2025
Seoul National University, Seoul National University, Seoul National University, Seoul National University, Seoul National University and Seoul National University
Downloads 42 (1,170,409)

Abstract:

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Critical heat flux, heaving motion, correlation, floating nuclear power plant, offshore reactor

8.

Experiments of Critical Heat Flux for Helical Finned Rod Under Rolling Conditions Using R-134a

Number of pages: 37 Posted: 26 Apr 2024
Seoul National University, Seoul National University, Seoul National University, Seoul National University, Seoul National University, Korea Institute of Nuclear Safety, Seoul National University and Seoul National University
Downloads 28 (1,345,526)

Abstract:

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Critical heat flux, Helical-finned heater, Rolling motion, Simulant fluid, Floating nuclear power plant

9.

Experimental investigation of flow boiling CHF under inclined annuli using heater rod with axially cosine-shaped power distribution

Number of pages: 38 Posted: 08 May 2026
Seoul National University, affiliation not provided to SSRN, Seoul National University, Seoul National University, Seoul National University, Seoul National University and Seoul National University
Downloads 19 (1,500,778)

Abstract:

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Critical heat flux, Non-uniform power, Inclination, Rolling, Floating nuclear power plant, Simulant fluid