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Results 161-170 of 176 (Search time: 0.009 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| DERIVATION OF A DRYOUT MODEL IN A PARTICLE DEBRIS BED WITH THE DRIFT-FLUX APPROACH Chang, Soon-Heung; KIM, SH, NUCLEAR SCIENCE AND ENGINEERING, v.91, no.4, pp.404 - 413, 1985 | |
| LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS Lee, Je-Whan; Jeong, Yong-Hoon; Chang, Yoon-Il; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.43, no.4, pp.383 - 390, 2011-08 | |
| A DIAGNOSTIC EXPERT SYSTEM FOR THE NUCLEAR-POWER-PLANT BASED ON THE HYBRID KNOWLEDGE APPROACH YANG, JO; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.36, no.6, pp.2450 - 2458, 1989-12 | |
| A DYNAMIC RELIABILITY MODEL FOR NUCLEAR-FUEL ELEMENT CHOI, KY; Chang, Soon-Heung; YOON, YK, RELIABILITY ENGINEERING SYSTEM SAFETY, v.31, no.1, pp.111 - 116, 1991 | |
| A CRITICAL HEAT-FLUX MODEL BASED ON MASS, ENERGY, AND MOMENTUM BALANCE FOR UPFLOW BOILING AT LOW QUALITIES Chang, Soon-Heung; LEE, KW, NUCLEAR ENGINEERING AND DESIGN, v.113, no.1, pp.35 - 50, 1989-04 | |
| Development of an environmental radiation analysis research capability in the UAE Kim, Sung-yeop; Kim, Chankyu; Lee, Kun Jai; Chang, Soon-Heung; Elmasri, Hasna; Beeley, Philip A., APPLIED RADIATION AND ISOTOPES, v.81, pp.190 - 195, 2013-11 | |
| Development of safety analysis methodology for moderator system failure of CANDU-6 reactor by thermal-hydraulics/physics coupling Kim, Jong Hyun; Jin, Dong Sik; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.263, pp.241 - 254, 2013-10 | |
| The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; Chang, Soon-Heung; Jeong, Yong Hoon; Jeong, Jae Jun, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.69, pp.86 - 98, 2015-12 | |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - Part 2 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.2, pp.143 - 143, 2005-11 | |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - part 1 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.1, pp.1 - 1, 2005-10 |
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