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| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Critical heat flux and onset of nucleate boiling tests in a finned rod bundle Chae, HT; Park, JH; Kim, H; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12 | |
| A procedure to predict subcooled-water-flow-boiling CHF in uniformly heated tubes for high-heat-flux applications Kwon, YM; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.130, no.3, pp.310 - 328, 2000-06 | |
| Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes Kim, CH; Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.14, pp.2868 - 2877, 2005-07 | |
| Visualization of a principle mechanism of critical heat flux in pool boiling Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12 | |
| Critical heat flux experiments on the reactor vessel wall using 2-D slice test section Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11 |
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