Browse "NE-Journal Papers(저널논문)" by Author Chang, Soon-Heung
Showing results 65 to 124 of 176
| 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 |
| Enhancement of critical heat flux using nano-fluids for Invessel Retention-External Vessel Cooling Pham, Q. T.; Kim, Tae-Il; Song, Sub Lee; Chang, Soon-Heung, APPLIED THERMAL ENGINEERING, v.35, pp.157 - 165, 2012-03 |
| ESTIMATION OF THE FISSION PRODUCTS, ACTINIDES AND TRITIUM OF HTR-10 Jeong, Hyedong; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.5, pp.729 - 738, 2009-06 |
| EXPERIMENTAL AND ANALYTICAL STUDY ON THE TIME-DEPENDENT REMOVAL EFFICIENCY OF METHYL-IODIDE BY AN IMPREGNATED CHARCOAL BED Chang, Soon-Heung; CHO, WJ, NUCLEAR TECHNOLOGY, v.68, no.2, pp.242 - 251, 1985 |
| Experimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids Lee, Kwi Lim; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3397 - 3404, 2010-10 |
| Experimental study of post-dryout with R-134a upward flow in smooth tube and rifled tubes Lee, Song Kyu; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.11-12, pp.3153 - 3163, 2008-06 |
| Experimental study on the effect of angles and positions of mixing vanes on CHF in a 2x2 rod bundle with working fluid R-134a Shin, BS; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.235, no.16, pp.1749 - 1759, 2005-07 |
| Experimental study on the heat transfer characteristics during the pressure transients under supercritical pressures Kang, Kyoung-Ho; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.52, no.21-22, pp.4946 - 4955, 2009-10 |
| FISA-2/WS, A COMPACT REAL-TIME SIMULATOR FOR 2-LOOP PRESSURIZED WATER-REACTOR PLANTS JEONG, JJ; OH, DY; No, Hee Cheon; Chang, Soon-Heung; CHO, SJ; JUN, HY; LEE, YK, NUCLEAR TECHNOLOGY, v.90, no.3, pp.356 - 370, 1990-06 |
| Flow analysis using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.33, no.11-12, pp.966 - 974, 2006-07 |
| Flow boiling CHF enhancement using Al2O3 nanofluid and an Al2O3 nanoparticle deposited tube Kim, Tae-Il; Chang, Won-Joon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.54, no.9-10, pp.2021 - 2025, 2011-04 |
| Flow boiling CHF enhancement with surfactant solutions under atmospheric pressure Jeong, Yong Hoon; Sarwar, Mohammad Sohail; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.7-8, pp.1913 - 1919, 2008-04 |
| Flow-induced vibration in two-phase flow with wire coil inserts Kim, Dae Hun; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, v.34, no.4, pp.325 - 332, 2008-04 |
| Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification Kang, Dong Gu; Jhung, Myung Jo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.241, no.1, pp.257 - 269, 2011-01 |
| Foreword Chang, Soon-Heung; Baek W.-P.; Rempe J., NUCLEAR TECHNOLOGY, v.152, no.2, pp.143, 2005-11 |
| Fourteen lessons learned from the successful nuclear power program of the Republic of Korea Choi, Sungyeol; Jun, Eunju; Hwang, IlSoon; Starz, Anne; Mazour, Tom; Chang, Soon-Heung; Burkart, Alex R, ENERGY POLICY, v.37, no.12, pp.5494 - 5508, 2009-12 |
| Fusion Licensing and Safety Studies in Korea Kim, Hyuck Jong; Kim, Hyung Chan; Kwon, Myeun; Heo, Gyunyoung; Hwang, In-Ju; Chang, Soon-Heung; Kim, Jong Kyung; et al, IEEE TRANSACTIONS ON PLASMA SCIENCE, v.42, no.3, pp.664 - 670, 2014-03 |
| 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 |
| Hybrid accident simulation methodology using artificial neural networks for nuclear power plants Choi, YJ; Kim, HK; Baek, WP; Chang, Soon-Heung, INFORMATION SCIENCES, v.160, no.1-4, pp.207 - 224, 2004-03 |
| Identification of reactor vessel failures using spatiotemporal neural networks Roh, CH; Chang, HS; Kim, HG; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.43, no.6, pp.3229 - 2, 1996-12 |
| Improved methodology for generation of axial flux shapes in digital core protection systems Lee, GC; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.29, no.7, pp.805 - 819, 2002-05 |
| Korea looks beyond the next generation Chang, Soon-Heung; No, Hee Cheon; Baek, WP; Lee, SI; Lee, SW, NUCLEAR ENGINEERING INTERNATIONAL, v.42, no.511, pp.12 - 12, 1997-02 |
| LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS Lee, Je-Whan; Jeong, Yong-Hoon; Chang, Yoon-Il; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.43, no.4, pp.383 - 390, 2011-08 |
| LOCA Uncertainty Analysis Using the Fourier Amplitude Sensitivity Test and the Stepwise Regression Technique Kim, Tae Woon; Lee, Byung Ho; Chang, Soon-Heung, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.53, pp.344 - 346, 1986 |
| Measurement of critical heat flux for narrow annuli submerged in saturated water Kim, SH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.41 - 48, 2000-06 |
Measurement of local two-phase flow parameters of nanofluids using conductivity double-sensor probe Park, Yu-Sun; Chang, Soon-Heung, NANOSCALE RESEARCH LETTERS, v.6, 2011-04 |
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Type
- 2,776 Article
Open Access
- 152 OA Article
Date issued
- 465 2020 - 2024
- 1,120 2010 - 2019
- 712 2000 - 2009
- 369 1990 - 1999
- 110 1980 - 1989