Browse "NE-Conference Papers(학술회의논문)" by Author 227
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| Calculation of Fission Products Inventory for HTR-10 Jeong, HD; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| CFD Analysis of Dry Storage System for CANDU Spent Fuel using Fluent 6.2 Shin, Byungsoo; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
| CFD Analysis of Natural Convective Non-Darcy Flow in Porous Medium Lee, J.; Shin, BS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| CFD Analysis on Critical Void Fraction in Round Tube under CHF Conditions Shin, BS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| CHF Enhancement in Flow Boiling at low mass flux using Al2O3 Nano-fluid Kim, Tae Il; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05 |
| CHF enhancement in flow boiling using Al2O3 nano-fluid and Al2O3 nano-particle deposited tube Kim, T.I.; Chang, W.J.; Chang, Soon-Heung, 2010 American Nuclear Society Annual Meeting and Embedded Topical Meetings, pp.649 - 650, American Nuclear Society, 2010-06-13 |
| CHF Enhancement in Flow Boiling using Al2O3 Nano-Fluid and Al2O3 Nano-Particle Deposited Tube Kim, TI; Chun, TH; Chang, Soon-Heung, 한국원자력학회 춘계학술대회, 한국원자력학회, 2010-05-27 |
| CHF Enhancement in the Flow Boiling R-134a by Adding Wire Nets to Inner Surfaces of a Round Tube Song, Sub Lee; Shin, BS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| CHF Enhancement of SiC-water Nanofluids in Pool Boiling Experiment Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, 2012 PBNC Proceddings of th 18th Pacific Basin Nuclear Conference, Pacific Nuclear Council, 2012-03-20 |
| CHF Enhancement under Pool Boiling Using Nanofluids Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
| CHF Experiment and CFD Analysis in 2*2 Rod Bundle with Swirl-Type Mixing Vane Shin, BS; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| CHF Experiments for IVR-EVC using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2002-05-23 |
| CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10-05 |
| CHF Experiments under Realistic Severe Accident Condition for IVR-ERVC Strategy Kim, TI; Park, HM; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| CHF Experiments using a 2-D Curved Test Section with Additives for IVR-ERVC Strategy Kim, TI; Park, HM; Chang, Soon-Heung, 2011 NURETH14, NURETH-14, 2011-09-25 |
| Classification and Assessment of CHF Data in Round Tubes at Low Velocities Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, pp.341 - 349, 1994 |
| Classification of Critical Heat Flux Patterns Based on Parametric Trends Using the Entropy Minimax Principle Baek, WP; Park, JW; Chang, Soon-Heung, International Conference on Multiphase Flow, pp.67 - 70, 1991 |
| Comparative Study on the Power Generation Options in Korea using Multi Criteria Decision Analysis Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27 |
| Computerization of Performance Test Procedures in Gori NPP Unit 3&4 Heo, GY; Lee, SJ; Lee, DG; Lee, JW; Park, JC; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2003 |
| CONCEPTUAL DESIGN AND ECONOMIC EVALUATION ABOUT THE COUPLING OF HIGH POWER PWRS AND DESALINATION SYSTEM Kim, Sang Ho; Kim, Hyeon Min; Heo, Gyun Young; Chang, Soon-Heung, 2012 PBNC Proceddings of th 18th Pacific Basin Nuclear Conference, Pacific Nuclear Council, 2012-03-20 |
| Conceptual Design of an Inherently Safe and Simple Tube Reactor Using Water as Moderator and Coolant Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactors, 1991 |
| Conceptual design of nuclear battery using semiconductor Chang, W.J.; Chang, Soon-Heung, 2004 American Nuclear Society Annual Meeting, v.90, pp.365 - 366, American Nuclear Society, 2004-06-13 |
| Conceptual Design Support System Based on Scale Laws for LMRs Chang, Soon-Heung, '97 ANS Winter Meeting, 1997 |
| Conservative Estimation of In-Vessel Retention for High Power Reactors Kim, Sang Ho; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21 |
| Continued Operation and Public Acceptance in Korea Jeong, Yong Hoon; Chang, Soon-Heung, The 27th JAIF-KAIF Seminar on Nuclear Industry, 2005-10-24 |
| Cost comparison of direct disposal vs. pyro-processing and DUPIC in Korea Lee, J.; Chang, Soon-Heung, 한국원자력학회 춘계학술대회, 한국원자력학회, 2010-05-27 |
| Cost-benefit Analysis Based on PSA for Additional Passive Safety System and Alternative AC Power Source Kim, Sang Ho; Kang, Hyun Gook; Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-04 |
| Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11 |
| Critical Heat Flux Enhancement: Nano-fluids and Others Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics, 2008-01-07 |
| Critical heat flux for downward flow boiling in a vertical narrow rectangular channel Lee, Juhyung; Daesung Jo; Heetaek Chae; Chang, Soon-Heung, 2013 ANS Winter Meeting and Technology Expo, American Nuclear Society, 2013-11-11 |
| Critical Heat flux for Natural-Circulation of Water Under Low Pressure Kim, YI; Chang, Soon-Heung, The 2nd International Conference on Multiphase Flow, pp.1 - 6, 1995 |
| Critical Heat Flux of Water in Vertical Round Tube at Low Pressure and Low Flow Conditions Kim, HC; Baek, WP; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998 |
| Critical Heat Flux of Water in Vertical Round Tubes at Low-Pressure and Low-Flow Conditions Park, JW; Kim, HC; Baek, WP; Chang, Soon-Heung, The 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997 |
| 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 |
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