Results 51-60 of 176 (Search time: 0.005 seconds).
NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
---|---|
OPTIMAL FUEL LOADING PATTERN DESIGN USING AN ARTIFICIAL NEURAL-NETWORK AND A FUZZY RULE-BASED SYSTEM KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.115, no.2, pp.152 - 163, 1993-10 | |
DEVELOPMENT STRATEGIES OF AN EXPERT SYSTEM FOR MULTIPLE ALARM PROCESSING AND DIAGNOSIS IN NUCLEAR-POWER-PLANTS CHEON, SW; Chang, Soon-Heung; CHUNG, HY, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.1, pp.21 - 30, 1993-02 | |
APPLICATION OF NEURAL NETWORKS TO MULTIPLE ALARM PROCESSING AND DIAGNOSIS IN NUCLEAR-POWER-PLANTS CHEON, SW; Chang, Soon-Heung; CHUNG, HY; Bien, Zeung nam, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.1, pp.11 - 20, 1993-02 | |
Risk analysis of radioactive waste repository based on the time dependent hazard rate Chang, Soon-Heung; Cho, WonJin, RADIOACTIVE WASTE MANAGEMENT AND THE NUCLEAR FUEL CYCLE, v.5, no.1, pp.63 - 80, 1984-06 | |
Foreword Chang, Soon-Heung; Baek W.-P.; Rempe J., NUCLEAR TECHNOLOGY, v.152, no.2, pp.143, 2005-11 | |
COBRA RELAP5 - A MERGED VERSION OF THE COBRA-TF AND RELAP5 MOD3 CODES LEE, SY; JEONG, JJ; KIM, SH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.99, no.2, pp.177 - 187, 1992-08 | |
NEURAL NETWORK MODEL FOR ESTIMATING DEPARTURE FROM NUCLEATE BOILING PERFORMANCE OF A PRESSURIZED WATER-REACTOR CORE KIM, HK; LEE, SH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.101, no.2, pp.111 - 122, 1993-02 | |
APPLICATION OF NEURAL NETWORKS TO A CONNECTIONIST EXPERT SYSTEM FOR TRANSIENT IDENTIFICATION IN NUCLEAR-POWER-PLANTS CHEON, SW; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.102, no.2, pp.177 - 191, 1993-05 | |
STRATEGY AND TOOL DEVELOPMENT FOR NUCLEAR-POWER-PLANT DESIGN SYNTHESIS WITH MEASUREMENT OF RELIABILITY AND SIMPLICITY MIN, BK; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.40, no.1, pp.69 - 76, 1993 | |
CLASSIFICATION AND PREDICTION OF THE CRITICAL HEAT-FLUX USING FUZZY THEORY AND ARTIFICIAL NEURAL NETWORKS MOON, SK; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.150, no.1, pp.151 - 161, 1994-09 |
Discover