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Dive into the research topics where Yeong Shin Jeong is active.

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Featured researches published by Yeong Shin Jeong.


Nuclear Technology | 2016

Development of Passive In-Core Cooling System for Nuclear Safety Using Hybrid Heat Pipe

Kyung Mo Kim; Yeong Shin Jeong; In Guk Kim; In Cheol Bang

Abstract The importance of passive safety for commercial nuclear power plants has been emphasized after the nuclear accidents that occurred at Three Mile Island and Fukushima. A combination of unexpected human errors, severe natural disasters, and defects of system designs led to the accidents, thereby highlighting the vulnerability of established safety systems of commercial nuclear power plants. Various passive safety systems are under development to mitigate design-basis accidents. However, several uncertainties and problems have been pointed out. As a solution to the problems, this paper proposes various designs for a passive in-core cooling system (PINCs) based on hybrid heat pipes. The feasibility and coolability of the PINCs as a passive safety system for commercial pressurized water reactors was investigated using experimental works and numerical analyses. The PINCs showed sufficient coolability to mitigate station blackout conditions by delaying core uncovery. Additionally, several PINCs concepts for advanced nuclear power plants such as a small modular reactor and Generation IV reactors are suggested.


International Journal of Heat and Mass Transfer | 2015

Comparison of thermal performances of water-filled, SiC nanofluid-filled and SiC nanoparticles-coated heat pipes

Kyung Mo Kim; Yeong Shin Jeong; In Guk Kim; In Cheol Bang


Applied Thermal Engineering | 2015

Hybrid heat pipe based passive in-core cooling system for advanced nuclear power plant

Yeong Shin Jeong; Kyung Mo Kim; In Guk Kim; In Cheol Bang


Applied Thermal Engineering | 2016

Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage cask

Yeong Shin Jeong; In Cheol Bang


Applied Thermal Engineering | 2017

Flow visualization and heat transfer performance of annular thermosyphon heat pipe

In Guk Kim; Kyung Mo Kim; Yeong Shin Jeong; In Cheol Bang


International Journal of Heat and Mass Transfer | 2016

Performance of annular flow path heat pipe with a polymer insert controlling compactness for energy applications

In Guk Kim; Kyung Mo Kim; Yeong Shin Jeong; In Cheol Bang


Journal of Fluid Machinery | 2014

CFD Analysis of a Concept of Nuclear Hybrid Heat Pipe with Control Rod

Yeong Shin Jeong; Kyung Mo Kim; In Guk Kim; In Cheol Bang


International Journal of Thermal Sciences | 2018

Natural convection heat transfer characteristics of molten salt with internal heat generation

Yeong Shin Jeong; Seok Bin Seo; In Cheol Bang


Annals of Nuclear Energy | 2018

Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer

Seong Dae Park; Han Seo; Yeong Shin Jeong; Dong Wook Jerng; In Cheol Bang


Annals of Nuclear Energy | 2018

Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

Seok Bin Seo; In Guk Kim; Kyung Mo Kim; Yeong Shin Jeong; In Cheol Bang

Collaboration


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In Cheol Bang

Ulsan National Institute of Science and Technology

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In Guk Kim

Ulsan National Institute of Science and Technology

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Kyung Mo Kim

Ulsan National Institute of Science and Technology

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Seok Bin Seo

Ulsan National Institute of Science and Technology

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Han Seo

Ulsan National Institute of Science and Technology

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Seong Dae Park

Ulsan National Institute of Science and Technology

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Hyo Heo

Ulsan National Institute of Science and Technology

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Ji Hyun Kim

Ulsan National Institute of Science and Technology

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Kyoung-Mo Kim

Ulsan National Institute of Science and Technology

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