Search
Results 11-18 of 18 (Search time: 0.004 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| 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 | |
| Proposed Concept of a Passive Water Cooled Reactor without Emergency Core Cooling System Baek, WP; Lee, GJ; Lee, JY; Chang, Soon-Heung, '92 International Conference on Design and Safety of Advanced Nuclear Power Plant, pp.1 - 6, 1992-10 | |
| Critical Heat Flux of Water in Vertical Round Tubes at Low-Pressure and Low-Flow Conditions Park, JW; Kim, HC; Baek, WP; Chang, Soon-Heung, The 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997 | |
| Critical Heat Flux of Water in Vertical Round Tube at Low Pressure and Low Flow Conditions Kim, HC; Baek, WP; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998 | |
| A Photographic Study on the Near-Wall Bubble Behavior in Subcooled Flow Boiling Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999 | |
| Development of Heated Length-to-Diameter Correction Factor for Critical Heat Flux Prediction Baek, WP; Lee, YH; Chang, Soon-Heung, The 9th International Topical Meeting on Nuclear Reactor Thermal Hydaulics, 1999 | |
| Experimental study of critical heat flux for low flow of water in vertical round tubes under low pressure Baek, WP; Park, JW; Chang, Soon-Heung, Winter Annual Meeting of the American Society of Mechanical Engineers, v.220, pp.35 - 43, American Society of Mechanical Engineers, 1992-11-08 | |
| Proposed Concept of a Water-Cooled Reactor with Passive Decay Heat Removal Capability Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting ot Review the Safety Features of New Reactor Design, 1991 |