Showing results 921 to 940 of 2779
Development of Nuclear Safety Culture evaluation method for an operation team based on the probabilistic approach Han, Sangmin; Lee, Seung Min; Yim, Ho Bin; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.111, pp.317 - 328, 2018-01 |
Development of Radionuclide Inventory Declaration Methods Using Scaling Factors for the Korean NPPs - Scope and Activity Determination Method - ki-ha hwang; sang-chul lee; sang-hee kang; kun jai lee, 방사성폐기물학회지, v.2, no.1, pp.77 - 85, 2004 |
DEVELOPMENT OF REAL-TIME CORE MONITORING-SYSTEM MODELS WITH ACCURACY-ENHANCED NEURAL NETWORKS KOO, BH; KIM, HC; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.5, pp.1347 - 1354, 1993-10 |
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 |
Development of scaling laws of heat removal and CFD assessment in concrete cask air path Kim, Hyeun Min; No, Hee-Cheon; Bang, Kyoung Sik; Seo, Ki Seog; Lee, Sang Hoon, NUCLEAR ENGINEERING AND DESIGN, v.278, pp.7 - 16, 2014-10 |
Development of Scan Survey Adjust Method for Radioactively Contaminated Sediment in Underwater Conditions Kim, Junha; Cho, Gyuseong; Jung-Jun Lee; Sang-Bum Hong; Eun-Joong Lee; Byung-Chae Lee; Bum-Kyung Seo, JOURNAL OF COASTAL RESEARCH, v.114, no.sp1, pp.325 - 329, 2021-10 |
DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT SUPPORTING SYSTEMS USING QUANTIFIED CONTAINMENT EVENT TREES Chang, HS; Kang, KS; Chang, Soon Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.48, no.3, pp.205 - 216, 1995 |
DEVELOPMENT OF SOFTWARE FOR THE MICROSIMULATOR FOR THE KO-RI-NUCLEAR-POWER-PLANT UNIT-2 SEOK, H; No, Hee Cheon; CHO, SJ; PARK, SD; JUN, HY; LEE, YK, NUCLEAR TECHNOLOGY, v.106, no.3, pp.384 - 396, 1994-06 |
Development of stability maps for flashing-induced instability in a passive containment cooling system for iPOWER Lim, Sang Gyu; No, Hee Cheon; Lee, Sang Won; Kim, Han Gon; Cheon, Jong; Lee, Jae Min; Ohk, Seung Min, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.1, pp.37 - 50, 2020-01 |
DEVELOPMENT OF STATISTICAL CORE THERMAL DESIGN METHODOLOGY USING A MODIFIED LATIN HYPERCUBE SAMPLING METHOD LEE, SH; KIM, HK; PARK, SR; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.94, no.3, pp.407 - 415, 1991-06 |
Development of Statistical Package for Uncertainty and Sensitivity Analysis(SPUSA) and Application to High Level Waste Repostitory System Kim, Tae-Woon; Cho, Won-Jin; Chang, Soon-Heung; Lee, Byung-Ho, NUCLEAR ENGINEERING AND TECHNOLOGY , v.19, no.4, pp.249 - 265, 1987 |
Development of supercritical CO2 turbomachinery off-design model using 1D mean-line method and Deep Neural Network Son, Seongmin; Jeong, Yongju; Cho, Seong Kuk; Lee, Jeong-Ik, APPLIED ENERGY, v.263, pp.114645, 2020-04 |
DEVELOPMENT OF THE ADVANCED PROCEDURE FOR EMERGENCY OPERATION USING TASK ALLOCATION AND SYNTHESIS OF PRA RESULTS KANG, KS; CHANG, HS; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.45, no.3, pp.249 - 259, 1994 |
DEVELOPMENT OF THE AUTOMATIC TEST PATTERN GENERATION FOR NPP DIGITAL ELECTRONIC-CIRCUITS USING THE DEGREE-OF-FREEDOM CONCEPT KIM, DS; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.42, no.4, pp.1429 - 2, 1995-08 |
DEVELOPMENT OF THE DYNAMIC FAULT TREE USING MARKOVIAN PROCESS AND SUPERCOMPONENT JEONG, KS; Chang, Soon-Heung; KIM, TW, RELIABILITY ENGINEERING SYSTEM SAFETY, v.19, no.2, pp.137 - 160, 1987 |
Development of the effectiveness measure for an advanced alarm system using signal detection theory Park, JK; Choi, SS; Hong, JH; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.44, no.2, pp.163 - 172, 1997-04 |
DEVELOPMENT OF THE FINITE-ELEMENT METHOD OF BODY FIT NODALIZATION FOR MIXED CONVECTION ANALYSIS IN ROD BUNDLES LEE, GJ; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.122, no.1-3, pp.195 - 208, 1990-09 |
Development of the LMFBR Accident Analysis Computer Code No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.47 - 57, 1984-01 |
Development of the once-through hybrid sulfur process for nuclear hydrogen production Jung, Yong Hun; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.35, no.22, pp.12255 - 12267, 2010-11 |
DEVELOPMENT OF THE ONLINE OPERATOR AID SYSTEM OASYS USING A RULE-BASED EXPERT-SYSTEM AND FUZZY-LOGIC FOR NUCLEAR-POWER-PLANTS Chang, Soon-Heung; KANG, KS; CHOI, SS; JEONG, HK; YI, CU, NUCLEAR TECHNOLOGY, v.112, no.2, pp.266 - 294, 1995-11 |
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