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Results 101-110 of 149 (Search time: 0.006 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Gravity-driven injection experiments and direct-contact condensation regime map for passive high-pressure injection system Lee, SI; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.183, no.3, pp.213 - 234, 1998-07 | |
| Measurements of void fraction by an improved multi-channel conductance void meter Song, CH; Chung, MK; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.184, no.2-3, pp.269 - 285, 1998-08 | |
| Boiloff pattern transition during core uncovery in a small break LOCA Lim, IC; No, Hee Cheon, ANNALS OF NUCLEAR ENERGY, v.23, no.18, pp.1459 - 1476, 1996-12 | |
| Mass transfer coefficient model for the analysis of volatile species transport between two phases Jeong, JH; No, Hee Cheon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.7, pp.907 - 918, 1997 | |
| INSTRUMENT FAILURE-DETECTION AND ESTIMATION METHODOLOGY FOR THE NUCLEAR-POWER-PLANT OH, DY; No, Hee Cheon, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.37, no.1, pp.21 - 30, 1990-02 | |
| INSTRUMENT FAILURE-DETECTION AND RECONSTRUCTION METHODOLOGY IN SPACE-TIME NUCLEAR-REACTOR DYNAMIC-SYSTEMS WITH FIXED IN-CORE DETECTORS OH, DY; No, Hee Cheon; KIM, SH, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.38, no.5, pp.1026 - 1034, 1991-10 | |
| A dry-spot model for transition boiling heat transfer in pool boiling Ha, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.41, no.23, pp.3771 - 3779, 1998-12 | |
| A disturbance wave instability model for annular-to-intermittent flow transition in vertical two-phase flow system Lim, IC; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.33, no.12, pp.903 - 914, 1996-12 | |
| Decay Heat Removal and Operators Intervention During A Very Small LOCA No, Hee Cheon, JOURNAL OF THE KOREAN NUCLEAR SOCIETY, v.16, no.1, pp.11 - 17, 1984-03 | |
| EFFECT OF HEAT-FLUX ON THE CONCENTRATION FACTOR IN CREVICES OF NUCLEAR STEAM-GENERATORS SHIN, SW; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.73, no.3, pp.378 - 383, 1986-06 |
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