Showing results 160 to 219 of 240
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 |
Quantification of Overestimated Risk on Nuclear Power by Using Probabilistic Weighted Function Song, Sub Lee; Chang, Soon-Heung, 2011 한국원자력학회 추계학술발표회, 한국원자력학회, 2011-10-27 |
Regulatory Framework for Controlling the Research Reactor Decommissioning Project Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
Research on Artificial Neural network Applications for Nuclear Power Plant Cheon, SW; Chang, Soon-Heung, '92 Conference Seminar on Human Cognitive and Cooperation Activities in Adv. Tech., 1992 |
Review on Visualization Results of DNB and Relations with Hypertheses of DNB Models Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2003 |
Safety Assessment on Vitrification Facility of Low- and Intermediate-Level Radioactive Wastes Heo, GY; Lee, SJ; Ji, PG; Maeng, SJ; Park, JG; Shin, SU; Chang, Soon-Heung, 한국원자력학회 2002년도 춘계공동학술발표회, 한국원자력학회, 2002 |
SBO Simulations for Integrated Passive Safety System (IPSS) Using MARS Kim, Sang Ho; Joung, Sung Yeop; Chang, Soon-Heung, 2012 한국원자력학회 추계학술발표회, 한국원자력학회, 2012-10-25 |
Software Development for Simplified Performance Tests and Weekly Performance Check in Younggwang NPP Unit 3&4 Heo, GY; Lee, JU; Kim, JT; Park, JC; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2002 |
Spacer Grid Effects on Post-CHF Heat Transfer in an Annulus Geometry Lee, KL; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
State Analysis of BOP Using Statistical and Heuristic Methods Heo, GY; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2003 |
Statistical Learning Framework with Adaptive Retraining for Condition-Based Maintenance An, SH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
Stepwise Grouping Algorithm for Statistical Learning Framework An, S.; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2009-10-29 |
Study on the Pressure Drop in the Helical Wire Inserted Tube Using FLUENT Code Park, Yusun; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
Surfactant effects on critical heat flux during flow boiling experiment Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 2007 Annual Meeting on American Nuclear Society, pp.491 - 492, 2007-06-24 |
The Development Strategies on an Integrated Operator Decision Aid Support System in Nuclear Power Plants Kang, KS; Jeong, HK; Yi, CU; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, pp.176 - 179, 1993 |
The Effect of the Inner Pressure Induced by Fission Gas on the SiC Layer Integrity Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-27 |
The Effect of Vibration on Critical Heat Flux in a Vertical Round Tube Lee, Y.H.; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, v.40, no.10, pp.734 - 743, 2002 |
The effects of swirl flow on CHF by various spacer grids in 2*2 rod bundle with R-134a Shin, B.S.; Chang, Soon-Heung, 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1520 - 1526, 2004-06-13 |
The Effects of Vibration on CHF Kim, DH; Lee, YH; Chang, Soon-Heung, NUTHOS 2004, 2004-10 |
The Multi-Dimensional Analysis Method Development for KALIMER-600 using MARS-LMR CODE Woo, Seung Min; Park, Hae Min; Chang, Soon-Heung; Jeong, Yong Hoon, International Conference on Fast Reactors and Related Fuel Cycles (FR09), 2009-12 |
The Multi-Dimensional Analysis Method Development for Sodium Pool of SFR using MARS-LMR CODE Woo, SM; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2009-10-29 |
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