Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Article

Showing results 921 to 940 of 2779

921
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

922
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

923
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

924
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

925
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

926
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

927
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

928
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

929
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

930
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

931
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

932
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

933
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

934
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

935
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

936
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

937
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

938
Development of the LMFBR Accident Analysis Computer Code

No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.2, pp.47 - 57, 1984-01

939
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

940
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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