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| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| DEVELOPMENT OF AN UNCERTAINTY QUANTIFICATION METHOD OF THE BEST ESTIMATE LARGE LOCA ANALYSIS PARK, SR; BAEK, WP; Chang, Soon-Heung; LEE, BH, NUCLEAR ENGINEERING AND DESIGN, v.135, no.3, pp.367 - 378, 1992-07 | |
| Genetic programming model for long-term forecasting of electric power demand Lee, DG; Lee, BW; Chang, Soon-Heung, ELECTRIC POWER SYSTEMS RESEARCH, v.40, no.1, pp.17 - 22, 1997-01 | |
| OPTIMAL TEST INTERVAL MODELING OF THE NUCLEAR SAFETY SYSTEM USING THE INHERENT UNAVAILABILITY AND HUMAN ERROR LEE, JH; Chang, Soon-Heung; YOON, WH; HONG, SY, NUCLEAR ENGINEERING AND DESIGN, v.122, no.1-3, pp.339 - 348, 1990-09 | |
| A STUDY OF CRITICAL HEAT-FLUX FOR LOW FLOW OF WATER IN VERTICAL ROUND TUBES UNDER LOW-PRESSURE Chang, Soon-Heung; Baek, WP; Bae, TM, NUCLEAR ENGINEERING AND DESIGN, v.132, no.2, pp.225 - 237, 1991-12 | |
| 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 | |
| An Improved Mechanistic Model to Predict Critical Heat Flux in Subcooled and Low Quality Convective Boiling Kwon, Young Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.31, no.2, pp.236 - 255, 1999-04 |
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