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Results 31-40 of 252 (Search time: 0.007 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Two-Phase Flow Modeling of Critical Heat Flux for Subcooled and Low-Quality Flow Boiling Kwon, YM; Suk, SD; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydaulics and Safety, 1998 | |
| New Flooding Correlation for Narrow Gap Geometry Kim, SH; Baek, WP; Chang, Soon-Heung, 2000 ANS Summer Meeting, 2000 | |
| Boiling and Critical Heat Flux Performance of Al2O3-Water Nano-Fluids From a Flat Surface in a Pool Bang, IC; Chang, Soon-Heung, 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, 2004 | |
| A Study on the Design Consideration of the Advanced Multi Purpose Canister Jun, EJ; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2004 | |
| Belief-Based Diagnosis Module for Turbine Cycles in NPPs Heo, GY; Chang, Soon-Heung, NUTHOS 2004, 2004-10 | |
| The Effects of Vibration on CHF Kim, DH; Lee, YH; Chang, Soon-Heung, NUTHOS 2004, 2004-10 | |
| Assessment of Dryout Heat Flux Correlations for Particle Beds Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01 | |
| Intelligent Software System for the Advanced Control Room of a Nuclear Power Plant Choi, SS; Park, JJ; Heo, GY; Kim, HG; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, pp.443 - 448, 한국원자력학회, 1997 | |
| KAIST Critical Heat Flux Correlation for Water Flow in Vertical Round Tubes Baek, WP; Kim, HG; Chang, Soon-Heung, The 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1997 | |
| Experimental Sutdy and Correlation Development of Critical Heat Flux Under Low Pressure and Low Flow condition Kim, HC; Baek, WP; Kim, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997 |
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