Jin-Seong Yoo

ORCID: 0000-0002-6042-0037
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About
Contact & Profiles
Research Areas
  • Heat Transfer and Boiling Studies
  • Nuclear Engineering Thermal-Hydraulics
  • Heat transfer and supercritical fluids
  • Spacecraft and Cryogenic Technologies
  • Nuclear reactor physics and engineering
  • Metallurgy and Material Forming
  • Metal Alloys Wear and Properties
  • Nuclear Materials and Properties
  • Microstructure and Mechanical Properties of Steels
  • Engineering Applied Research
  • Fluid Dynamics and Mixing
  • Fusion materials and technologies
  • Cyclone Separators and Fluid Dynamics
  • Erosion and Abrasive Machining
  • Refrigeration and Air Conditioning Technologies
  • Combustion and Detonation Processes
  • Heat Transfer and Optimization

Seoul National University
2000-2024

10.1016/s0140-7007(99)00047-x article FR International Journal of Refrigeration 2000-05-01

The wall film-wise condensation plays an important role in the heat transfer processes of exchangers, refrigerators, and air conditioner. In field nuclear engineering, steam is often utilized safety systems to remove core decay under both transient accident conditions. particular, passive containment cooling system (PCCS), are designed ensure severe A computational fluid dynamics (CFD) scale analysis has been conducted calculate rate PCCS. However, despite increase computing power, there...

10.1016/j.net.2021.03.001 article EN cc-by-nc-nd Nuclear Engineering and Technology 2021-03-07

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10.2139/ssrn.4689318 preprint EN 2024-01-01

Recently, diverse marine applications of nuclear power are being considered to meet the carbon reduction goals in maritime industries. One distinctive characteristics reactors is limit space and it requires high density. To address this problem, tight lattice bundle with a helical shaped non-circular fuel rods can be employed. However, critical heat flux (CHF) mechanisms for such alternative have not been adequately investigated experimentally. In particular, no open-access CHF experiment...

10.2139/ssrn.4449851 preprint EN 2023-01-01

In a floating nuclear reactor, the prediction of critical heat flux (CHF) is crucial because CHF can be influenced under heaving, rolling, and inclination conditions compared with case in land-based reactor. Therefore, existing empirical correlations invalid some marine this study, flow boiling were proposed to predict rolling motions tubes annuli. Available experimental databases collected, their trends analyzed. According previous studies, inclined was generally reduced but enhanced The...

10.2139/ssrn.4268855 article EN SSRN Electronic Journal 2022-01-01

Floating nuclear power plants have attracted significant attention as a prospective means to deliver clean energy, particularly in geographically remote areas where conventional infrastructure is inaccessible. The ocean environment, however, can affect the thermal-hydraulic phenomena them. Notably, two-phase system, CHF change due periodic variation of additional forces. While few experimental studies been conducted on under heaving motion, expanding range test conditions necessary elucidate...

10.2139/ssrn.4542801 preprint EN 2023-01-01
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