Researcher Page

사진

Jeong, Yong Hoon (정용훈) C-1680-2011

Department
Department of Nuclear and Quantum Engineering(원자력및양자공학과)
Website
http://necel.kaist.ac.krHomePage
Research Area
nuclear system design and safety analysis, nuclear hydrogen, desalination, electric vehicle, power transport system

Keyword Cloud

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1

Effect of dimensions and downward-facing angle on CHF under atmospheric condition

Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.102, pp.603 - 610, 2019-04

2

CHF correlation development under ERVC conditions by using the local liquid velocity from PIV measurements

Yoon, Jongwoong; Kam, Dong Hoon; Park, Hae Min; et al, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.128, pp.171 - 184, 2019-01

3

CHF experiment with downward-facing carbon and stainless steel plates under pressurized conditions

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.125, pp.670 - 680, 2018-10

4

Critical heat flux model on a downward facing surface for application to the IVR conditions

Park, Hae Min; Jeong, Yong Hoonresearcher; Carnevali, Sofia, NUCLEAR ENGINEERING AND DESIGN, v.330, pp.317 - 324, 2018-04

5

Flow boiling CHF enhancement by wettability and flow conditions in a slug flow in the rectangular curved channel

Park, Hae Min; Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.91, pp.388 - 398, 2018-02

6

Fluid-to-fluid scaling criteria development for modeling high pressure steam condensation in horizontal tubes

Khasawneh, Khalid; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.116, pp.1266 - 1281, 2018-01

7

Critical heat flux on downward-facing carbon steel flat plates under atmospheric condition

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.90, pp.22 - 27, 2018-01

8

Safety evaluation of supercritical CO2 cooled micro modular reactor

Oh, Bong Seong; Ahn, Yoon Han; Yu, Hwanyeal; et al, ANNALS OF NUCLEAR ENERGY, v.110, pp.1202 - 1216, 2017-12

9

Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure

Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heungresearcher; et al, ANNALS OF NUCLEAR ENERGY, v.109, pp.498 - 506, 2017-11

10

Analysis of CHF enhancement by magnetite nanoparticle deposition in the subcooled flow boiling region

Choi, Young Jae; Kam, Dong Hoon; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.109, pp.1191 - 1199, 2017-06

11

Improving power and desalination capabilities of a large nuclear power plant with supercritical CO2 power technology

Lee, Won Woong; Bae, Seong Jun; Jung, Yong Hun; et al, DESALINATION, v.409, pp.136 - 145, 2017-05

12

A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region

Kim, Seong Gu; Yu, HwanYeal; Moon, Jangsik; et al, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.41, no.4, pp.512 - 525, 2017-03

13

Development of analytical model for solar chimney power plant with and without water storage system

Choi, Young Jae; Kam, Dong Hoon; Park, Yoon Won; et al, ENERGY, v.112, pp.200 - 207, 2016-10

14

Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion

Nam, Seung Hyun; Venneri, Paolo; Kim, Yongheeresearcher; et al, PROGRESS IN NUCLEAR ENERGY, v.91, pp.183 - 207, 2016-08

15

Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels

Choi, Gil Sik; Chang, Soon Heungresearcher; Jeong, Yong Hoonresearcher, NUCLEAR ENGINEERING AND DESIGN, v.303, pp.1 - 16, 2016-07

16

Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels

Choi, Gil Sik; Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, Transactions of the Korean Society of Mechanical Engineers, v.39, no.12, pp.953 - 963, 2015-12

17

A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA

Kim, Sang Ho; Chang, Soon Heungresearcher; Choi, Yu Jung; et al, NUCLEAR ENGINEERING AND DESIGN, v.295, pp.346 - 359, 2015-12

18

A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel

Choi, Gil Sik; Jeong, Yong Hoonresearcher; Chang, Soon Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.294, pp.103 - 116, 2015-12

19

The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel

Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; et al, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.69, pp.86 - 98, 2015-12

20

INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR

Nam, Seung Hyun; Venneri, Paolo; Kim, Yongheeresearcher; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.6, pp.678 - 699, 2015-10

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