Browse "NE-Journal Papers(저널논문)" by Author Chang, Soon-Heung
Showing results 40 to 99 of 176
| Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a pool Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.12, pp.2407 - 2419, 2005-06 |
| CHF characteristics of R-134a flowing upward in uniformly heated vertical tube Kim, CH; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.11, pp.2242 - 2249, 2005-05 |
| CHF detection using spationtemporal neural network and wavelet transform Kim, SH; Bang, IC; Baek, WP; Chang, Soon-Heung; Moon, SK, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.27, no.2, pp.285 - 292, 2000-02 |
| CHF enhancement in flow boiling system with TSP and boric acid solutions under atmospheric pressure Lee, Juno; Jeong, Yong-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3594 - 3600, 2010-10 |
| CHF enhancement of SiC nanofluid in pool boiling experiment Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.52, pp.12 - 18, 2014-01 |
| CHF experiment and CFD analysis in a 2 x 3 rod bundle with mixing vane Shin, Byung Soo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.239, no.5, pp.899 - 912, 2009-05 |
| CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy Kim, Tae-Il; Park, Hae-Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.243, pp.272 - 278, 2012-02 |
| 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 |
| CLASSIFICATION OF CRITICAL HEAT-FLUX PATTERNS USING ENTROPY MINIMAX PRINCIPLE Chang, Soon-Heung; BAEK, WP; PARK, JW, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.18, no.2, pp.185 - 193, 1991 |
| 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 |
| Cognitive simulation of operators diagnostic strategies in nuclear power plants Cheon S.W.; Lee J.W.; Sim B.S.; Park J.K.; Chang, Soon-Heung, INFORMATICA (LJUBLJANA), v.21, no.2, pp.201 - 207, 1997-06 |
| Comparative cost analysis of direct disposal versus pyro-processing with DUPIC in Korea Lee, Je-Whan; Lee, Jeong-Ik; Chang, Won-Joon; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.37, no.12, pp.1699 - 1704, 2010-12 |
| Comparative study on state analysis of BOP in NPPs Heo, G; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.50, no.4, pp.1271 - 1281, 2003-08 |
| COMPARATIVE-STUDY ON UNCERTAINTY AND SENSITIVITY ANALYSIS AND APPLICATION TO LOCA MODEL KIM, TW; Chang, Soon-Heung; LEE, BH, RELIABILITY ENGINEERING SYSTEM SAFETY, v.21, no.1, pp.1 - 26, 1988 |
| Cost benefit analysis of advanced nuclear fuel cycle using Linear Programming optimization Lee, Je-Whan; Chang, Yoon-Il; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.46, pp.116 - 120, 2012-08 |
| Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow Park, C; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.4, pp.453 - 464, 1997 |
| Critical heat flux and flow pattern for water flow in annular geometry Park, JW; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.172, no.1-2, pp.137 - 155, 1997 |
| Critical heat flux and onset of nucleate boiling tests in a finned rod bundle Chae, HT; Park, JH; Kim, H; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12 |
| CRITICAL HEAT FLUX ENHANCEMENT Chang, Soon-Heung; Jeong, Yong Hoon; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11 |
| Critical heat flux experiments on the reactor vessel wall using 2-D slice test section Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11 |
| Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions Park, C; Chang, Soon-Heung; Baek, WP, NUCLEAR ENGINEERING AND DESIGN, v.183, no.3, pp.235 - 247, 1998-07 |
| Critical heat flux of water in vertical round tubes at low pressure and low flow conditions Kim, HC; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.49 - 73, 2000-06 |
| Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes Kim, CH; Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.14, pp.2868 - 2877, 2005-07 |
| Critical heat flux prediction using genetic programming for water flow in vertical round tubes Lee, DG; Kim, HG; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.7, pp.919 - 929, 1997 |
| Critical heat flux under flow oscillation of a water at low-pressure, low-flow conditions Kim, YI; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.193, no.1-2, pp.131 - 143, 1999-09 |
| 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 |
| Derivation of mechanistic critical heat flux model for water based on flow instabilities Chang, Soon-Heung; Kim, YI; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.8, pp.1109 - 1119, 1996-12 |
| Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants Chang, Soon-Heung; Kim, Sang Ho; Choi, Jae Young, NUCLEAR ENGINEERING AND DESIGN, v.260, pp.104 - 120, 2013-07 |
| Detection of process anomalies using an improved statistical learning framework An, Sang Ha; Heo, Gyunyoung; Chang, Soon-Heung, EXPERT SYSTEMS WITH APPLICATIONS, v.38, no.3, pp.1356 - 1363, 2011-03 |
| Development of a back propagation network for one-step transient DNBR calculations Kim, HC; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.24, no.17, pp.1437 - 1446, 1997 |
| DEVELOPMENT OF A BUNDLE CORRECTION METHOD AND ITS APPLICATION TO PREDICTING CHF IN ROD BUNDLES HWANG, DH; BAEK, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.139, no.2, pp.205 - 220, 1993-02 |
| DEVELOPMENT OF A COMBINED ALGORITHM OF ONLINE INSTRUMENT FAILURE-DETECTION WITH AN IMPROVED GENERALIZED LIKELIHOOD RATIO METHOD AND SUBOPTIMAL CONTROL ON A PWR PRESSURIZER CHUNG, HY; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.74, no.2, pp.113 - 131, 1986-08 |
| Development of a method of evaluating an inventory of fission products for a pebble bed reactor Jeong, Hyedong; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.35, no.12, pp.2161 - 2171, 2008-12 |
| Development of a need-oriented steam turbine cycle simulation toolbox Heo, G; Chang, Soon-Heung; Choi, SS, IEEE TRANSACTIONS ON ENERGY CONVERSION, v.20, no.4, pp.859 - 869, 2005-12 |
| DEVELOPMENT OF A PHENOMENOLOGICAL MODEL FOR THE PREDICTION OF DRYOUT LOCATIONS UNDER FLOODING-LIMITED CRITICAL HEAT-FLUX CONDITIONS HWANG, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.148, no.2-3, pp.475 - 486, 1994-07 |
| Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels Han, KH; Seo, KW; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.2, pp.164 - 178, 2006-01 |
| Development of a thermal-hydraulic analysis code for annular fuel assemblies Han, KH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.226, no.3, pp.267 - 275, 2003-12 |
| Development of an advanced human-machine interface for next generation nuclear power plants Chang, Soon-Heung; Choi, SS; Park, JK; Heo, GY; Kim, HG, RELIABILITY ENGINEERING SYSTEM SAFETY, v.64, no.1, pp.109 - 126, 1999-04 |
| 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 AN EXPERT SYSTEM FOR FAILURE DIAGNOSIS OF PRIMARY SIDE SYSTEMS CHEON, SW; KIM, HG; KIM, WJ; MIN, BK; Chang, Soon-Heung; CHUNG, HY, NUCLEAR TECHNOLOGY, v.97, no.1, pp.1 - 15, 1992-01 |
| DEVELOPMENT OF AN EXPERT SYSTEM FOR THE DESIGN SYNTHESIS AND RELIABILITY ASSESSMENT MIN, BK; Chang, Soon-Heung, NUCLEAR SCIENCE AND ENGINEERING, v.100, no.4, pp.426 - 434, 1988-12 |
| DEVELOPMENT OF AN ONLINE FUZZY EXPERT-SYSTEM FOR INTEGRATED ALARM PROCESSING IN NUCLEAR-POWER-PLANTS CHOI, SS; KANG, KS; KIM, HG; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.42, no.4, pp.1418 - 2, 1995-08 |
| 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 |
| Development of conceptual design tool for liquid metal cooled-reactors Lee, KG; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.26, no.18, pp.1657 - 1668, 1999-12 |
| 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 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 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 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 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 |
| 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 |
| Development strategies of an intelligent human-machine interface for next generation nuclear power plants Choi, SS; Park, JK; Hong, JH; Kim, HG; Chang, Soon-Heung; Kang, KS, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.43, no.3, pp.2114 - 3, 1996-06 |
| DEVELOPMENT STRATEGIES ON AN INTEGRATED OPERATOR DECISION AID SUPPORT SYSTEM FOR NUCLEAR-POWER-PLANTS KANG, KS; KIM, HG; Chang, Soon-Heung; JEONG, HK; PARK, SD, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.4, pp.1304 - 2, 1993-08 |
| DIAGNOSTIC STRATEGIES OF A PROTOTYPE EXPERT SYSTEM FOR MALFUNCTION DIAGNOSIS OF PRIMARY-SIDE SYSTEMS IN NUCLEAR-POWER-PLANT CHUNG, HY; PARK, IS; HUR, SK; CHEON, SW; KIM, HG; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF ELECTRICAL POWER ENERGY SYSTEMS, v.14, no.4, pp.284 - 297, 1992-08 |
| Direct observation of a liquid film under a vapor environment in a pool boiling using a nanofluid Bang, IC; Chang, Soon-Heung; Baek, WP, APPLIED PHYSICS LETTERS, v.86, no.13, pp.382 - 388, 2005-03 |
| Effects of mechanical vibration on critical heat flux in vertical annulus tube Kim, Dae Hun; Lee, Yong Ho; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.237, no.9, pp.982 - 987, 2007-05 |
| Effects of the spacer and mixing vanes on critical heat flux for low-pressure water at low-velocities Chung, JB; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.6, pp.757 - 765, 1996-10 |
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