Visualization of Droplet Breakup with Unquenched Spacer Grid during Reflood Phase of APR1400
Hee Cheon No , Chul-Hwa Song , Chang Wook Shin , Eo Hwak Lee
Transactions of the American Nuclear Society 103 ( 1) 843 -844
2010
Hybrid Methodology of Deterministic and Probabilistic Safety Assessment Focusing on DSA
Hee Cheon No , Bokyung Kim
Transactions 120 ( 1) 581 -582
2019
A Zero-Dimensional Model for Dryout Heat Flux of Debris Bed Considering Interfacial Friction Between Two Phases
Hee Cheon No , Dong Yeol Yeo
Transactions 120 ( 1) 1162 -1164
2019
Recession of CVD Silicon Carbide in Steam Environment
Hee Cheon No , Byung Ha Park
Transactions 119 ( 1) 959 -961
2018
Thermal-hydraulic characteristics evaluations of the printed circuit heat exchanger in a helium-water test loop
Hee Cheon No , I.H. Kim
International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 1749 -1757
2010
Modeling of in-vessel gap cooling and its validation against LAVA, ALPHA, and LMP200 experiments
Hee Cheon No , Moon Won Song , Dongyeol Yeo
Nuclear Engineering and Design 374 111028
2021
Potential improvements of supercritical CO2 Brayton cycle by mixing other gases
Hee Cheon No , Jeong Ik Lee , WooSeok Jeong , Yong Hoon Jeong
International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 448 -458
1
2010
Development of a two-dimensional coupled-implicit numerical tool for the optimal design of CDI electrodes
Byong Guk Jeon , Hee Cheon No , Jeong Ik Lee
Desalination 274 ( 1) 226 -236
13
2011
On the formulation of the virtual mass term in two fluid models
Mujid S. Kazimi , Hee Cheon No
Nuclear Engineering and Design 95 163 -170
1
1986
An improved numerical scheme with the fully-implicit two-fluid model for a fast-running system code
Jae Jun Jeong , Hee Cheon No
Nuclear Engineering and Design 104 ( 2) 145 -153
5
1987
Effect of interfacial drag force on the numerical stability of the two-step method in the two-fluid model
Jae Young Lee , Hee Cheon No
Nuclear Engineering and Design 126 ( 3) 427 -438
3
1991
Quantitative evaluation of swelling or shrinking level contributions in steam generators using spectrum analysis
Man Gyun Na , Hee Cheon No
Annals of Nuclear Energy 20 ( 10) 659 -666
17
1993
Thermal hydraulic behavior in the deteriorated turbulent heat transfer regime for a gas-cooled reactor
Hyeonil Kim , Jeong Ik Lee , Hee Cheon No
Nuclear Engineering and Design 240 ( 4) 783 -795
16
2010
An intermediate heat exchanging–depressurizing loop for nuclear hydrogen production
Young Soo Kim , Hee Cheon No , Ho Joon Yoon , Jeong Ik Lee
Nuclear Engineering and Design 240 ( 10) 2957 -2962
3
2010
Full-scope simulation of a dry storage cask using computational fluid dynamics
Seung Hun Yoo , Hee Cheon No , Hyeun Min Kim , Eo Hwak Lee
Nuclear Engineering and Design 240 ( 12) 4111 -4122
15
2010
Development of scaling laws of heat removal and CFD assessment in concrete cask air path
Hyeun Min Kim , Hee Cheon No , Kyoung Sik Bang , Ki Seog Seo
Nuclear Engineering and Design 278 7 -16
7
2014
Stratified flow-induced air-ingress accident assessment of the GAMMA code in HTGRs
Hyung Gon Jin , Hee Cheon No , Hyeon Il Kim
Nuclear Engineering and Design 241 ( 8) 3216 -3223
11
2011
Physical model development and optimal design of PCHE for intermediate heat exchangers in HTGRs
In Hun Kim , Hee Cheon No
Nuclear Engineering and Design 243 243 -250
52
2012
Effects of the onset time of natural circulation on safety in an air ingress accident involving a HTGR
Hyung Gon Jin , Hee Cheon No , Byung Ha Park
Nuclear Engineering and Design 250 626 -632
4
2012
Potential sodium–CO2 interaction of a supercritical CO2 power conversion option coupled with an SFR: Basic nature and design issues
Jae-Hyuk Eoh , Hee Cheon No , Yong-Bum Lee , Seong-O Kim
Nuclear Engineering and Design 259 88 -101
16
2013