Browse "NE-Conference Papers(학술회의논문)" by Author 227
Showing results 189 to 240 of 240
| 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 |
| The Predictive Model on the User Reaction Time Using the Information Similarity Lee, SJ; Heo, GY; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| The Two Step Characteristic Method to Reduce Numerical Diffusion Golay, MW; Chang, Soon-Heung, 1983 American Nuclear Society Mathematics and Computation Topical Meeting, American Nuclear Society, 1983 |
| Thermal hydraulic analysis of annular fuel-based assemblies Han, K.H.; Chang, Soon-Heung, 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1583 - 1589, 2004-06-13 |
| Thermal Hydraulic Analysis of Gas-Cooled Reactors with Annular Fuel Rods Han, KH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Thermal Hydraulic Analysis of Thorium Fuel Assemblies Loaded with Annular Seed Pins Han, KH; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2002 |
| Thermal Hydraulic Analysis of Thorium-based Annular Fuel Assemblies Han, KH; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10 |
| Thermal Hydraulic Design Parameters Study for Severe Accidents Using Neural Network Roh, CH; Chang, KS; Chang, Soon-Heung, The 6th International Conference on Nuclear Engineering, 1998 |
| Thermal Performance Test through On-line Turbine Cycle Performance Monitoring in Nuclear Power Plants Heo, GY; Lee, SJ; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999 |
| Thermal Power Estimation Using De-noising and an Autoassociative Neural Network in Nuclear Power Plant Heo, GY; Choi, SS; Chang, Soon-Heung, '98 ANS Winter Meeting, ANS, 1998 |
| Thermal-hydraulic analysis of annular fuel-based assemblies of liquid metal reactors Han, K.-H.; Chang, Soon-Heung, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.1, pp.38 - 46, American Nuclear Society, 2005-05-15 |
| Thermal-hydraulic Analysis of the GT-MHR Core using Axiomatic Design Jeong, HD; Chang, Soon-Heung, NUTHOS-7, 2008-10-05 |
| Time Dependent Analysis of Quenching Phemonenon with the Nonuniformity of Water Penetration Pattern in Hot Debris Bed Lee, KW; Chang, Soon-Heung, The 2nd International Topical Meeting on Nucl. Power Plant Ther. Hydrau. and Operation, pp.26 - 33, 1986-04 |
| To Mars and Beyond with Nuclear Power - Design Concept of Korea Advanced Nuclear Thermal Engine Rocket Nam, Seung Hyun; Chang, Soon-Heung, 2013 한국원자력학회 춘계학술발표회, 한국원자력학회, 2013-05-30 |
| Toward Unification of Critical Heat Flux Prediction Models for Flow Boiling Based on the Liquid Film Dryout Mechanism Kim, HC; Baek, WP; Chang, Soon-Heung, The 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, 2000 |
| Two-Phase Flow Modeling of Critical Heat Flux for Subcooled and Low-Quality Flow Boiling Kwon, YM; Suk, SD; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydaulics and Safety, 1998 |
| Ubiquitous Computing for Complex Plant An, SH; Chang, WJ; Chang, Soon-Heung, 한국차세대컴퓨팅학회 학술발표회, 한국차세대컴퓨팅학회, 2006 |
| Vibration characteristics of a vertical round tube according to heat transfer regimes Lee, Y.H.; Chang, Soon-Heung; Baek, W.-P., 10th International Conference on Nuclear Engineering (ICONE 10), v.3, pp.187 - 193, 2002-04-14 |
| Web-based Turbine Cycle Performance Analysis for Nuclear Power Plants Heo, GY; Lee, SJ; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000 |
| Wettability of Heated Surfaces under Pool Boiling using Surfactant Solutions and Nanofluids Chang, Won Joon; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-11 |
| 결정론적 및 확률론적 안전분석을 위한 격납용기해석 Chang, Soon-Heung, 1983년 국내외 한국과학기술 학술회의 (원자력안전성 기술분과), pp.199 - 203, 1982 |
| 전원별 종합적 비교평가를 위한 웹기반 설문지 설계 이성진; 안상하; 김태운; 김성호; 하재주; 장순흥, 한국에너지공학회 2004년도 추계 학술발표회, 한국에너지공학회, 2004 |
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