Browse "NE-Conference Papers(학술회의논문)" by Author 227
Showing results 140 to 199 of 240
| 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 |
| Nuclear Safety and Public Acceptance Baek, WP; Chang, Soon-Heung, The 7th Nuclear Energy Symposium (NES-7), 2002 |
| Numerical Analysis of Characteristics of a Particulate Debris Bed Coolability with Single Phase Flow Lee, J.; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| Numerical Study on the Thermal Behavior of Reactor Vessel Lower Head in Ex-Vessel Cooling Yang, SH; Baek,k WP; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995-01-01 |
| On-line Monitoring Interface Development for Turbine Cycle Thermal Performance Test in Nuclear Power Plants Heo, GY; Lee, SJ; Chang, Soon-Heung, CSEPC 2000, 2000 |
| Onset of Nucleate Boiling for Downward Flow in Narrow Rectangular Channel under Low Pressure Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-11), American Nuclear Society, 2016-10-11 |
| Optimal Test Interval Modeling of Nuclear Safety System Using the Inherent Unavailability and Human Error Lee, JH; Yoon, WH; Hong, SY; Chang, Soon-Heung, The 3rd Internation Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operation, 1988 |
| Overall Energy Policy and the Comprehensive Nuclear Promotion Plan of Korea Chang, Soon-Heung; Jeong, Yong Hoon, The Symbio Open Symposium on Nuclear Power Development, 2006-03-10 |
| Passive Strategy with Integrated Passive Safety System (IPSS) for DBAs in SBO Kim, Sang Ho; 김지희; Choi, Jae Young; 전인섭; 장순흥, 2013 한국원자력학회 추계학술발표회, 한국원자력학회, 2013-10-24 |
| Performance Test of the Quenching Meshes for Hydrogen Control Hong, S.-W.; Shin, Y.-S.; Song, J.-H.; Chang, Soon-Heung, Journal of Nuclear Science and Technology, v.40, no.10, pp.814 - 819, 2003-10 |
| Perspective on Critical Heat Flux Research for Reactor Desigh and Safety Baek, WP; Chang, Soon-Heung, The 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1997 |
| Physical Modeling and Finite Element Method for the Analysis of Lateral Phase Distribution Phenomena Lee, GJ; Chang, Soon-Heung, International Conference on Multiphase Flow, Tsukuba, 1991 |
| Post-CHF Heat Transfer characteristics in one rod bundle geometry Lee, KL; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2006-11 |
| Prediction of Critical Heat Flux in Highly Subcooled Covective Boiling Kwon, YM; Chang, Soon-Heung, The 9th International Topical Meeting on Nuclear Reactor Thermal Hydaulics, 1999 |
| Prediction of Nuclear Reactor Parameters Using Artificial Neural Network Models Roh, MS; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 2nd International Forum on the Expert Systems and Computer Simulation in Energy Eng., 1992-03 |
| Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application 남승현; 이정익; 장순흥, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-30 |
| Premature and Stable Critical Heat Flux for Downward Flow in a Narrow Rectangular Channel Lee, Juhyung; Jo, Dae Seong; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| Proposed Concept of a Passive Water Cooled Reactor without Emergency Core Cooling System Baek, WP; Lee, GJ; Lee, JY; Chang, Soon-Heung, '92 International Conference on Design and Safety of Advanced Nuclear Power Plant, pp.1 - 6, 1992-10 |
| Proposed Concept of a Water-Cooled Reactor with Passive Decay Heat Removal Capability Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting ot Review the Safety Features of New Reactor Design, 1991 |
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Date issued
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- 2,529 2010 - 2019
- 1,629 2000 - 2009
- 723 1990 - 1999
- 172 1980 - 1989