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Showing results 1 to 13 of 13

1
Analysis of Flow Instabilities in Multi-channel Loop Type Thermosyphon

You, Byung-Hyun; Jeong, Yong Hoon, 2014 22nd International Conference on Nuclear Engineering (ICONE22), ASME, 2014-07-11

2
Application of computational fluid dynamics codes for nuclear reactor design

You, Byung-Hyun; Moon, Jangsik; Jeong, Yong Hoon, International Electronic Journal of Nuclear Safety and Simulation, v.6, no.3, pp.226 - 233, 2015-09

3
Assessment of advanced RANS models ability to predict a turbulent swept liquid metal flow over a wire in a channel

You, Byung-Hyun; Jeong, Yong Hoon; Addad, Yacine, NUCLEAR ENGINEERING AND DESIGN, v.353, 2019-11

4
Assessment of two-equation and second-moment closures for flow and energy predictions in wire-wrapped sub-channel of liquid metal reactor using unstructured finite volume codes = 비정렬 유한 체적 코드를 활용한 2-방정식 및 2차 모멘트 닫힘 난류모델의 액체금속로 부수로 내 유동 및 에너지 예측 평가link

You, Byung-Hyun; 유병현; et al, 한국과학기술원, 2017

5
Design and Evaluation of Passive Decay-heat Removal System Using Mercury Thermosyphon

You, Byung-Hyun; Jeong, Yong Hoon, 2013 ANS Annual Meeting, American Nuclear Society, 2013-06-20

6
Design and Evaluation of Passive Decay-heat Removal System Using Mercury Thermosyphon

You, Byung-Hyun; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-16

7
Design of Passive Decay Heat Removal System using Mercury Thermosyphon for SFR

You, Byung-Hyun; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-24

8
Design of Passive Decay Heat Removal System Using Thermosyphon for Low Temperature and Low Pressure Pool Type LWR

Moon, Jangsik; You, Byung-Hyun; Jung, Yong Hun; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-25

9
Experimental Validation of PRHR System for Low Temperature and Low Pressure Pool-type LWR Using Thermosyphon

Moon, Jangsik; You, Byung-Hyun; Jung, Yong Hun; Jeong, Yong Hoon, 2014 22nd International Conference on Nuclear Engineering (ICONE22), ASME, 2014-07-11

10
Numerical Study for Turbulent Heat Transfer in Helical Wired Sub-channel Flow Regime of Duct-less Assembly in SFR

You, Byung-Hyun; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

11
RANS Simulation of Turbulent Swept Flow Over a Wire in a Channel for Core Thermal Hydraulic Design

You, Byung-Hyun; Jeong, Yong-Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-19

12
RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design

You, Byung-Hyun; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01

13
Validation of 1-D Code Developed to Analyze Passive Decay Heat Removal System Using Thermosyphon for Low Temperature and Low Pressure Pool-type LWR

Moon, Jangsik; You, Byung-Hyun; Jung, Yong Hun; Jeong, Yong Hoon, 2014 International Congress on Advances in Nuclear Power Plants, American Nuclear Society, 2014-04-09

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