Browse "NE-Conference Papers(학술회의논문)" by Author 227
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| 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 |
| INTEGRATED APPROACH TO EVALUATE CONTAINMENT HEAT TRANSFER COEFFICIENTS. Chang, Soon-Heung; Choi, JH, 1984 American Nuclear Society Annual Meeting, v.46, pp.490 - 491, American Nuclear Society, 1984 |
| Integrated Assessment of National Power Sources Using AHP Technique Kim, SH; Kim, TW; Ha, JJ; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Integrated Passive Safety System (IPSS) for Ultimate Safe Nuclear Power Plants Chang, Soon-Heung; Kim, Sang Ho; Choi, Jae Young, 2012 한국원자력학회 춘계학술발표회, 한국원자력학회, 2012-05-17 |
| Intelligent Software System for the Advanced Control Room of a Nuclear Power Plant Choi, SS; Park, JJ; Heo, GY; Kim, HG; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, pp.443 - 448, 한국원자력학회, 1997 |
| Investigation Thermal-Hydraulic Design Parameters for Severe Accidents Using Neural Networks and Analytic Hierarchies Roh, CH; Chang, Soon-Heung, '99 ANS Summer Meeting, pp.177 - 179, ANS, 1999 |
| IRWST Elevation Change for Passive In-vessel Retention Strategy Kim, Sang Ho; Lee, Juno; 장순흥, 2011 한국원자력학회 추계학술발표회, 한국원자력학회, 2011-10-28 |
| Issue and Software Development for NPP Turbine Cycle Performance Tests Heo, GY; Lee, SJ; Chang, Soon-Heung, International Symposium on the Future I&C for NPP, 2002 |
| KAIST Critical Heat Flux Correlation for Water Flow in Vertical Round Tubes Baek, WP; Kim, HG; Chang, Soon-Heung, The 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1997 |
| Linear Programming Optimization of Nuclear fuel cycle in Korea Lee, J.; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| Market Penetration Simulation of Hydrogen Powered Vehicles in Korea Jun, EJ; Chang, Soon-Heung, 2006 International Congress on Advances in Nuclear Power Plants, pp.2315 - 2321, 2006-06 |
| Market Penetration Simulation of Hydrogen Powered Vehicles in Korea Jen, Eun Ju; Jeong Yong Hoon; Chang, Soon-Heung, American Nuclear Society 2006 Summer Meeting, American Nuclear Society, 2006-06-04 |
| Mass Flux and Gap Effects on the CHF Experiments for IVR-EVC using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002-10-13 |
| Measuring the Social Value of Nuclear Energy using Contingent Valuation Methodology Jun, EJ; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| Mechanistic Flux Model of the Inverted Annular Film Boiling Ho, S.; Chang, Soon-Heung, The 9th International Heat Transfer Conference, pp.431 - 436, 1990 |
| Monte Carlo calculation for Modeling HTR-10 core Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| Multi-Dimensional Analysis in steady state for Sodium Hot Pool using MARS-LMR Woo, SM; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| Nano-particle deposition and wettability change in pool boiling Jeong, Yong Hoon; Chang, Won Joon; Chang, Soon-Heung, 2007 Annual Meeting on American Nuclear Society, pp.489 - 490, 2007-06-24 |
| Nanofluid Application : Liquid Sublayer Structure and Heat Transfer Mechanism Bang, IC; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Natural Circulation of the Encapsulated Nuclear Heat Source Lee, KG; Chang, Soon-Heung, 2000 ANS Winter Meeting, ANS, 2000 |
| New Approach for Classifying and Prediction Critical Heat Using Fuzzy Theory and Artificial Neural Network Moon, SK; Chang, Soon-Heung, The 2nd International Conference on Multiphase Flow, pp.33 - 40, 1995 |
| New Flooding Correlation for Narrow Gap Geometry Kim, SH; Baek, WP; Chang, Soon-Heung, 2000 ANS Summer Meeting, 2000 |
| Non-Heating Simulation of Pool-Boiling Critical Heat Flux Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, American Nuclear Society 2002 Annual Meeting, American Nuclear Society, 2002-06-09 |
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