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| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Experimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids Lee, Kwi Lim; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3397 - 3404, 2010-10 | |
| Radial basis function networks applied to DNBR calculation in digital core protection systems Lee, GC; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.30, no.15, pp.1561 - 1572, 2003-10 | |
| A photographic study on the near-wall bubble behavior in subcooled flow boiling Chang, Soon-Heung; Bang, IC; Baek, WP, INTERNATIONAL JOURNAL OF THERMAL SCIENCES, v.41, no.7, pp.609 - 618, 2002-07 | |
| An improved physical model for flooding limited CHF under zero and very low flow conditions Park, C; Hwang, DH; Chang, Soon-Heung; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.25, no.3, pp.339 - 348, 1998-04 | |
| A mechanistic critical heat flux model for wide range of subcooled and low quality flow boiling Kwon, YM; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.188, no.1, pp.27 - 47, 1999-04 | |
| Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.109, pp.498 - 506, 2017-11 | |
| Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel Al Hammadi, Rashid; Yi, Yongsun; Zaki, Wael; Cho, Pyungyeon; Jang, Changheui, NUCLEAR ENGINEERING AND DESIGN, v.301, pp.24 - 31, 2016-05 | |
| A dry-spot model of critical heat flux applicable to both pool boiling and subcooled forced convection boiling Ha, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.43, no.2, pp.241 - 250, 2000-01 | |
| Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363, 2004-09 | |
| Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02 |
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