Browse "NE-Conference Papers(학술회의논문)" by Author 227
Showing results 100 to 159 of 240
| Design of Graphic Aggregation Model for Evaluation of Energy Systems An, Sang Ha; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
| Design of Nuclear Power Plant Online Monitoring System An, Sang-ha; Lee, Song-kyu; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10 |
| Design of Reactor Coolant Pump Seal Online Monitoring System Ah, SH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| Development of a Customized Steam Turbine Cycle Simulation Toolbox Heo, GY; Choi, SS; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10 |
| Development of a Heated Length-to-Diameter Correction Factor for Critical Heat Flux Prediction Lee, YH; Baek, WP; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998 |
| Development of a Reactor Vessel Failure Diagnosis System for Accident Management No, CH; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995 |
| Development of an Environmental Radiation Analysis Research Capability in the UAE Kim, Sung-yeop; Kim, Changkyu; Lee, Kun Jai; Chang, Soon-Heung; Elmasri, Hasna; Beeley, Philip A., 6th International Conference on Radionuclide Metrology Low-Level-Radioactivity Measurement Techniques, 한국표준과학연구원, 2012-09-19 |
| Development of an Expert System for Malfuction Diagnosis of Primary System in Nuclear Power Plant Chung, HY; Park, IS; Hur, SK; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 3rd Symposium on Expert Systems Application to Power Systems, pp.539 - 547, 1991-04 |
| Development of an Integrated Knowledge-Base and its Management Tool for Comupterized Alarm Processing System 장순흥, KNS Spring Meeting, 1997 |
| Development of an On-Line Expert System for Integrated Alarm Processing in Nuclear Power Plants Kim, HG; Choi, SS; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.121 - 123, 1994 |
| Development of Finite Element Method of Body Fit Nodalization for Mixed Convection Analysis in Rod Bunbles Lee, GJ; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Reactor Plant Thermal Hydraulics and Operation, 1988 |
| Development of Heat Exchanger Thermal Performance Monitoring Program Ha, AS; Heo, GY; Han, KH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Development of Heated Length-to-Diameter Correction Factor for Critical Heat Flux Prediction Baek, WP; Lee, YH; Chang, Soon-Heung, The 9th International Topical Meeting on Nuclear Reactor Thermal Hydaulics, 1999 |
| Development of nuclear power plant online monitoring system using statistical quality control An, Sang Ha; Jeong, Yong Hoon; Chang, Soon-Heung, 2006 Winter Meeting of the American Nuclear Society, pp.932 - 934, American Nuclear Society, 2006-11-12 |
| Development of OASYS Using Rule- and Fuzzy-Based Expert System for Nuclear Power Plants Kang, KS; Choi, SS; Kim, HG; Chang, Soon-Heung, '94 ANS Winter Meeting, pp.119 - 121, 1994 |
| Development of Performance Aanlysis Support Modules in Younggwang NPP Unit 3&4 Heo, GY; Lee, SJ; Choi, SS; Choi, GH; Jee, MH; Heo, I.; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2003 |
| Development of Performance Meassure for Advanced Alarm System Using Signal Detection Theory Park, JK; Choi, SS; Chang, Soon-Heung, '96 CSEPC, 1996 |
| Development of Regulation Concept for Nuclear Fusion Reactor Kim, TI; Jeong, H; Lee, Joo Hyung; Song, Sub Lee; Chang, Soon-Heung, 한국원자력학회 추계학술대회, 한국원자력학회, 2010-05-27 |
| Development of the Distinctiveness Measure for a CRT based Information Display System using Excess Entropy Concept Park, JK; Lee, SJ; Chang, Soon-Heung, CSEPC 2000, 2000 |
| Development of Thermal-Hydraulic Analysis Code for Annular Fuel-Based Assemblies Han, KH; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002 |
| 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, '96 NPIC & HMIT, 1996 |
| Development Strategies on an Intelligent Software System for Total Operation and Maintenance of Nuclear Power Plants Kim, HG; Choi, SS; Chang, Soon-Heung, The 7th International Conference on Human-Computer Interaction, 1997 |
| Effect of application SiC fuel cladding for mitigating focusing effect in situation of IVR Song, Sub Lee; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| Effect of Mixing Vane on Critical Heat Flux in 2x3 Rod Bundle with R-134a Chang, Soon-Heung; Shin, BS, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2007-05 |
| Effect of Vibration on CHF in Vertical Annulus at Atmosphere Kim, DH; Lee, YH; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002 |
| Effects of mechanical vibration on Critical Heat Flux in vertical annulus Kim, DH; Lee, YH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2003 |
| Effects of Mechanical Vibraton on CHF in Vertical Annulus Kim, DH; Lee, YH; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10 |
| Effects of Surface Inclination Angle and Size on Critical Heat Flux Yang, SH; Baek, WP; Chang, Soon-Heung, '97 ANS Winter Meeting, ANS, 1997 |
| Estimation of Fission Product Release from the TRISO Fuel Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
| Estimation of fission product release from TRISO Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, 2006 Winter Meeting of the American Nuclear Society, pp.858 - 859, American Nuclear Society, 2006-11-12 |
| Estimation of Fission Products Plate-out Throughout Gas-cooling Loop Systems Jeong, HD; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| Estimation ofthe Thermal Efficiency of Hybrid Sulfur Cycle for Hydrogen Generation using Gas Cooled Reactor Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27 |
| Experimental and Analytical Study on the Simulation of Pool Boiling CHF Based on Macrolayer Dryout Model Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
| Experimental Study for the CHF Characteristics of the Vertical Tube Using R-134a Kim, CH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004 |
| experimental study of CHF and post-CHF phenomena on flow boiling of R-134a with grid effects in annular geometry Lee, KL; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| Experimental study of critical heat flux for low flow of water in vertical round tubes under low pressure Baek, WP; Park, JW; Chang, Soon-Heung, Winter Annual Meeting of the American Society of Mechanical Engineers, v.220, pp.35 - 43, American Society of Mechanical Engineers, 1992-11-08 |
| Experimental Study on CHF Enhancement for Investigating Relationship among Surface Characteristics by Using Hierarchical Porous Surface Song, Sub Lee; Kim, Jae Joon; Lee, Eun Je; Chang, Soon-Heung; Cho, Sung Oh, 2012 PBNC Proceddings of th 18th Pacific Basin Nuclear Conference, Pacific Nuclear Council, 2012-03-20 |
| Experimental Sutdy and Correlation Development of Critical Heat Flux Under Low Pressure and Low Flow condition Kim, HC; Baek, WP; Kim, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997 |
| Expert System for Nuclear Power Plant Performance Evaluation and Diagnosis Kang, KS; Cheon, SW; Chang, Soon-Heung, IEEE Fifth Conference on Human Factors and Power Plants, IEEE, 1992-06 |
| Exploratory Study on Safety Objectives of the Fusion DEMO Plant Lee, Juhyung; An, Sang Ha; Kim, Tae Il; Chang, Soon-Heung, 2011 한국원자력학회 추계학술발표회, 한국원자력학회, 2011-10-27 |
| Fast Running System Code Development with Analytical Solution Technique and Marching Scheme Whang, DH; Lee, BH; Chang, Soon-Heung, '85 ANS National Heat Transfer Conference, pp.141 - 150, ANS, 1985-08 |
| Feasibility Study of Technology-neutral Regulatory Framework for Fusion Power Choi, Jae Young; Lee, Juhyung; Kim, Tae Il; Chang, Soon Heung, 2012 한국원자력학회 춘계학술발표회, 한국원자력학회, 2012-05-17 |
| Feasibility Study on Two-phase Thermosipon for External Vessel Cooling Application of SFR 최재영; 송섭리; 장순흥, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| Feedwater Flowrate Monitoring Using the Advanced Signal Processing Based on De-noising and Principal Component Analysis in Nuclear Power Plans Heo, GY; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, pp.105 -, 한국원자력학회, 1998 |
| Fission Product Release from TRISO by Diffusion Chang, Won Joon; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-27 |
| Flow Analysis in the Helical Wire Inserted Tube using CFD code Park, YS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05 |
| Flow Boiling CHF Enhancement using Porous Surface Coatings Sawar, M. Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-26 |
| Flow Boiling CHF Experiments using Nanofluid under Different Heating Rate Kim, TI; Jee, YT; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2011-05-26 |
| Flow Boiling CHF Experiments using Nanofluid under Different Heating Rate Kim, Tae Il; Lee, Joo Hyung; Chang, Soon-Heung, 2011 The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), WORTH-5, 2011-10-11 |
| Flow Boiling Experiment for the Heat Transfer Enhancement Using Nanoporous Coatings Sarwar, M.S.; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Flow Induced Vibration Characteristics in 2X3 Bundle Critical Heat Flux Experiment Kim, DH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Flow Instability and Critical Heat Flux for Downward Flow in a Vertical Narrow Rectangular Channel Heated From Both-sides Lee, Juhyung; Daesung Jo; Soon Heung Chang, 2013 한국원자력학회 추계학술발표회, 한국원자력학회, 2013-10-25 |
| Flow Structure and Near-Wall Bubble Behavior in Subcooled Flow Boiling at High Heat Flux Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000 |
| Fuel Options for Vehicles in Korea and Role of Nuclear Energy Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28 |
| Future Light Water Reactor Development Programs in Korea Baek, WP; Chang, Soon-Heung, Tht 2nd Japan-Korea Seminar on Advanced Reactors, 1996 |
| Grid effects on the post-CHF heat transfer in one rod bundle geometry Lee, KL; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2007-05 |
| Growth of Bubble layer and Onset of Flow Instability in a vertical Narrow rectangular channel 이주형; 장순흥; 정용훈, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2015-05-08 |
| Heat Flux Enhancement using Particle-mixed Coolant in HTGR Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-03 |
| Historical Overview of NPP Accident Source Term Analyses 김성엽; Choi, Jae Young; Philip A. Beeley; 이건재; 장순흥, 2013 한국방사성폐기물학회 추계학술발표회, 한국방사성폐기물학회, 2013-10-17 |
| Hydrogen Combustion Experiments for Equipment Protection using Quenching Mesh Hong, SW; Shin, YS; Song, JH; Kim, HD; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10 |
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