Showing results 1 to 4 of 4
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 |
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 |
Assessment of a tube-based bundle CHF prediction method using a subchannel code Chun, TH; Hwang, DH; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.25, no.14, pp.1159 - 1168, 1998-09 |
Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01 |
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