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In-Cheol Chu
Observed names:
Chu In-Cheol,
In Cheol Chu,
In-Cheol CHU,
Incheol Chu
Institution:
Korea Atomic Energy Research Institute
Observed institutions:
Korea Atomic Energy Research Institute,
Korea Advanced Institute of Science and Technology,
Korea University of Science and Technology
OpenAlex ID:
A5113531959
Visualization of boiling structure and critical heat flux phenomenon for a narrow heating surface in a horizontal pool of saturated water
2013
·
In-Cheol Chu
, Hee Cheon NO
, et al.
·
International Journal of Heat and Mass Transfer
·
79
Bubble Lift-off Diameter and Nucleation Frequency in Vertical Subcooled Boiling Flow
2011
·
In-Cheol CHU
, Hee Cheon NO
, et al.
·
Journal of Nuclear Science and Technology
·
64
PDF
Observation of critical heat flux mechanism in horizontal pool boiling of saturated water
2014
·
In-Cheol Chu
, Hee Cheon NO
, et al.
·
Nuclear Engineering and Design
·
58
A mechanistic model for predicting the maximum diameter of vapor bubbles in a subcooled boiling flow
2015
·
Nhan Hien Hoang
, In-Cheol Chu
, et al.
·
International Journal of Heat and Mass Transfer
·
51
A bubble dynamics-based model for wall heat flux partitioning during nucleate flow boiling
2017
·
Nhan Hien Hoang
, Chul-Hwa Song
, et al.
·
International Journal of Heat and Mass Transfer
·
43
Development of passive flow controlling safety injection tank for APR1400
2007
·
In-Cheol Chu
, Chul-Hwa Song
, et al.
·
Nuclear Engineering and Design
·
38
Local heat transfer during reflux condensation mode in a U-tube with and without noncondensible gases
2006
·
Kyung-Won Lee
, Hee Cheon NO
, et al.
·
International Journal of Heat and Mass Transfer
·
36
Flow-induced vibration of nuclear steam generator U-tubes in two-phase flow
2011
·
In-Cheol Chu
, Heung June Chung
, et al.
·
Nuclear Engineering and Design
·
35
Mechanism study of departure of nucleate boiling on forced convective channel flow boiling
2018
·
Seol Ha Kim
, In Cheol Chu
, et al.
·
International Journal of Heat and Mass Transfer
·
33
Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel
2016
·
In-Cheol Chu
, Seung-Jun Lee
, et al.
·
Nuclear Engineering and Design
·
32
Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus during LBLOCA Reflood Phase with a Direct Vessel Injection Mode
2003
·
Tae-Soon Kwon
, Byong-Jo Yun
, et al.
·
Nuclear Technology
·
28
Air-Water Countercurrent Flow Limitation in a Horizontal Pipe Connected to an Inclined Riser
1999
·
Seong-Kwon Kang
, In-Cheol Chu
, et al.
·
Nuclear Engineering and Technology
·
28
Fluid-elastic Instability of Rotated Square Tube Array in an Air-water Two-phase Crossflow
2006
·
Heung June Chung
, In-Cheol Chu
·
Nuclear Engineering and Technology
·
27
Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions
2013
·
Kihwan Kim
, Dong-Jin Euh
, et al.
·
Nuclear Engineering and Design
·
22
Interfacial condensation for countercurrent steam–water stratified wavy flow in a horizontal circular pipe
2006
·
Kyung-Won Lee
, In-Cheol Chu
, et al.
·
International Journal of Heat and Mass Transfer
·
20
Interfacial Condensation Heat Transfer for Countercurrent Steam-Water Stratified Flow in a Circular Pipe
2000
·
In-Cheol Chu
, Moon Ki Chung
, et al.
·
Nuclear Engineering and Technology
·
16
Experimental and numerical investigation of local bubble parameters for subcooled flow boiling in a pressurized annulus
2022
·
Yazan Alatrash
, Yun-Je Cho
, et al.
·
International Journal of Heat and Mass Transfer
·
10
Fluid-Elastic Instability of Rotated Square Array U-Tubes in Air-Water Flow
2009
·
In-Cheol Chu
, Heung June Chung
, et al.
·
Journal of Pressure Vessel Technology
·
10
Direct observation of rewetting failure mechanism at CHF under different subcooled flows
2020
·
Moonhee Choi
, In-Cheol Chu
, et al.
·
International Journal of Heat and Mass Transfer
·
9
Experimental identification for flow distribution inside APR+ reactor vessel and direction of internal structure design improvement
2015
·
Dongjin Euh
, Kihwan Kim
, et al.
·
Journal of Nuclear Science and Technology
·
4
PDF
Integral Effect Tests on Transient Thermal-Hydraulic Behavior during a Steam Generator Tube Rupture Accident in the APR1400
2012
·
Kyoung-Ho Kang
, Hyun-Sik Park
, et al.
·
Nuclear Technology
·
4
Fluid-Elastic Instability in Tube Bundles and Effect of Flow Regime Transition
2006
·
In-Cheol Chu
, Heung June Chung
, et al.
·
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy
·
4
A Simultaneous Observation of Bubble Growth and Microlayer Behavior for an Isolated Boiling Regime of Saturated Water
2011
·
No Hee Cheon
, In-Cheol Chu
, et al.
·
3
A Novel Semi-Empirical Correlation for Wall Heat Transfer During Saturated Nucleate Flow Boiling
2017
·
Nhan Hien Hoang
, Chul-Hwa Song
, et al.
·
ASME Journal of Heat and Mass Transfer
·
2
Application of Visualization Techniques to the Boiling Structures of Subcooled Boiling Flow and Critical Heat Flux = 과냉 비등유동 및 임계 열유속의 비등구조에 대한 가시화 기법의 적용
2011
·
In-Cheol Chu
, 주인철
·
2
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Works count:
37
Citation count:
660
H-index:
16
I10-index:
18
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