Browse "NE-Conference Papers(학술회의논문)" by Author 227
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| A Case Study of Risk Informed Asset Management (RIAM) for Nuclear Power Plant Lee,Gyoung Cheol; Jeong, Yong Hoon; Chang, Soon-Heung; Chung, Dae-Wook, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-02 |
| A Cooling Model Evaluation from the Quenching Mesh for Hydrogen Control Hong, SW; Song, JH; Kim, HD; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004 |
| A Digital Photographic Study on Nucleate Boiling in Subcooled Flow Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001 |
| A digital photographic study on nucleate boiling in subcooled flow for water and refrigerant 134A fluids Bang, I.C.; Baek, W.-P.; Chang, Soon-Heung, 10th International Conference on Nuclear Engineering (ICONE 10), v.3, pp.155 - 162, 2002-04-14 |
| A heterogeneous thorium fuel core design for enhanced fuel cycle economy Bae, K.-M.; Kim, M.-H.; Han, K.-H.; Chang, Soon-Heung, Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy, pp.1413 - 1420, 2003-11-16 |
| A Mechanistic CHF Model for Liquid Metals Based on Flow Excursion Mechanism Lee, YB; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactor, 1994 |
| A Methodology for Assessment of External Vessel Cooling During Severe Accidents in PWRs Park, JH; Baek, WP; Jeong, YH; Chang, Soon-Heung, Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, 2000-10-01 |
| A Methodology for Assessment of External Vessel Cooling During Severe Accidents in PWRs Park, Jae Hong; Baek, Won Pil; Jeong Yong Hoon; Chang, Soon-Heung, Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS2), v.Volume 1, pp.494 - 500, 2000-10-15 |
| A Modified CHF Correlation for Low Flow of Water at Low Pressures Baek, WP; Moon, SK; Chang, Soon-Heung, International Symposium on Two-Phase Flow Modeling and Experimentation, 1995 |
| A New Correlation for Counter-Current Flow Limited CHF in Narrow Rectangular Channels Lee, Ju Hyung; Chang, Soon-Heung, 한국원자력학회 춘계학술발표회, 한국원자력학회, 2011-05-26 |
| A New correlation of CHF under Counter-Current Flow in Narrow Rectangular Channels Lee, Ju Hyung; Chang, Soon-Heung, The 8th KSME-JSME Thermal and Fluids Engineering Conference, TFEC8, 2012-03-20 |
| A New Method for Cognitive Reliability Assessment Using Improved PSFs Modeling Han, YT; Kim, JW; Chang, Soon-Heung, CSEPC 2000, 2000 |
| A Numerical and Experimental Investigation of the Single-Phase Natural Circulation with Multiloop Baek, WP; Chang, Soon-Heung, International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting, pp.1 - 10, 1984 |
| A Photographic Study on Flow Boiling of R-134a in a Vertical Channel Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 2002년도 춘계공동학술발표회, 한국원자력학회, 2002 |
| A Photographic Study on Flow Boiling of R-134a in a Vertical Channel Baek, WP; Chang, Soon-Heung, 2000 Annual Meeting American Nuclear Society, American Nuclear Society, 2002-06 |
| A Photographic Study on the Near-Wall Bubble Behavior in Subcooled Flow Boiling Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999 |
| A Preliminary Experimental Study on Flow Boiling CHF Characteristics of Ballooned Channel KIM, YONG JIN; Song, Sub Lee; 문상기; 장순흥, 2013 한국원자력학회 추계학술발표회, 한국원자력학회, 2013-10-24 |
| A Preliminary Study on the Resuspension of Radionuclides in Desert Environment Kim, Sung Yeop; Beeley , Philip A.; Chang, Soon-Heung; Yim, Man-Sung, 2014 KNS Annual Spring Conference, Korean Nuclear Society, 2014-05-30 |
| A Qualitative Study on Low Public Acceptance of Nuclear Power in Terms of Communication Problems Song, Sub Lee; Kim, Sang Ho; Chang, Soon-Heung, 한국원자력학회 춘계학술발표회, 한국원자력학회, 2011-05-26 |
| A Refined Mechanistic Critical Heat Flux Model for Upflow Boiling at Low Qualities Lee, KW; Chang, Soon-Heung, The 9th International Heat Transfer Conference, Jerusalem, pp.141 - 146, 1990 |
| A Severe Accident Management Supporting system Using Quantified Containment Event Trees Chang, HS; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995 |
| A Study of the Predictive Model on the User Reaction Time using the Information Amount and Similarity Lee, SJ; Heo, GY; Chang, Soon-Heung, NUTHOS 2004, 2004-10 |
| A study of the predictive model on the user reaction time using the information amount andits similarity Lee, SJ; Heo, GY; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2004 |
| A Study on Natural Circulation of Pb-Bi Coolant and Decay Heat Removal System for Encapsulated Nuclear Heat Source Lee, KG; Chun, MH; No, HC; Chang, Soon-Heung, The 4th Japan-Korea Seminar on Advance Reactors, 2000 |
| A Study on System State Analyzer for Turbine Cycle Performance Test Heo, GY; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001 |
| A study on the conceptual design of a 1,500 MWe passive PWR with annular fuel Lee, K.L.; Chang, Soon-Heung, 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.22 - 27, 2004-06-13 |
| A Study on the Conceptual Design of a 1,500 MWe Passive PWR with Annular Fuel Lee, KL; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004 |
| A Study on the Correlations Development for Film boiling Heat Transfer on Spheres Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1998-05-01 |
| A Study on the Design Consideration of the Advanced Multi Purpose Canister Jun, EJ; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2004 |
| A Study on the Development of On-Line Source Term Estimation System for PWRs Kim, TW; Jeong, Yong Hoon; Choi, SS; Cho, GW; Shin, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
| A Study on the Effect of Various Spacer Grids on CHF in 2*2 rod Bundle with R-134a Shin, BS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2003 |
| A Study on the Non-Heating CHF Experiments Using Drilled Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1999-05-28 |
| A Study on the Non-Heating Simulation ofPool Boiling CHF on Flat Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000-10-26 |
| A Study on the Optimal Fuel Loading Pattern Design in Pressurized Water Reactor Using the Artificial Neural Network and Fuzzy Rule Based System Lee, BH; Kim, HG; Chang, Soon-Heung, The IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Rea, 1994 |
| Algebraic Model for Root-Cause Diagnosis in Nuclear Turbine Cycles Heo, GY; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004 |
| An application of zeta potential method for the selection of nano-fluids to enhance IVR capability Trang, P.Q.; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05-21 |
| An Experimental study of Fullerene (C60) Nano-fluids on Pool Boiling Conditions Melani, A.; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2009-10-29 |
| An Experimental Study of the Dropwise Condensation on Physically Processed Surface Choi, Jae Young; Chang, Soon-Heung; Watanabe, Noriyuki; Sambuichi, Takumi; Shiota, Daichi; Aritomi, Masanori, 2013 한국원자력학회 춘계학술발표회, 한국원자력학회, 2013-05-30 |
| An Experimental Study of the Effects of the Mixing Vane on Air-Water Mixed Flow Kim, SH; Baek, WP; Chang, Soon-Heung, The 6th International Conference on Nuclear Engineering, 1998 |
| An Experimental Study of the Pool-Boiling Chf on Downward-Facing Plates Yang, SH; Baek, WP; Chang, Soon-Heung, International Symposium on Two-Phase Flow Modeling and Experimentation, 1995 |
| An Experimental Study on Flow Boiling CHF Characteristics of Partially Narrowed Tube 송섭리; 김용진; Moon, Sang Ki; 장순흥, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| An Experimental Study on Flow Boiling Critical Heat Flux Characteristics of Suddenly Expanded Region 김용진; 송섭리; Moon, Sang Ki; 장순흥, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| An Experimental study on Onset of Flow Instability for Downward flow within Narrow rectangular channels Lee, Juhyung; Song, Jung-hyun; Chang, Soon Heung, 2012 한국원자력학회 추계학술발표회, 한국원자력학회, 2012-10-26 |
| An Experimental Study on Pool Boiling CHF with Hierarchical Porous Surface Fabricated by PMMA Coating and Electron Irraciation Song, Sub Lee; Kim, Jae Joon; Cho, Sung Oh; Chang, Soon-Heung, 2012 한국원자력학회 춘계학술발표회, 한국원자력학회, 2012-05-18 |
| An Experimental Study on the Convective Heat Transfer in Narrow Rectangular Channels for Downward Flow to Predict Onset of Nucleate Boiling Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| An Experimental Study on the Flow Instabilities and Critical Heat Flux under Natural Circulation Kim, YI; Chang, Soon-Heung, The 4th Internation Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1994-04 |
| An Experimental Work on the relation between flow Structure and CHF by Various Spacer Grids in 2*2 Rod Bundle with R-134a Shin, BS; Chang, Soon-Heung, The 10th international Topical meeting on Nuclear Reactor Thermal Hydraulics, 2003-10 |
| An Improved and Simplified DNB Model Based on Mass, Energy, and Momentum Balance Equations Lee, KW; Sul, YS; Baik, SJ; Han, SK; Chang, Soon-Heung, The 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, 1996 |
| An Improved Cost-Benefit Criterion Using Utility Theory Ra, KY; Chang, Soon-Heung, 1984 American Nuclear Society Annual Meeting, v.46, pp.523 - 525, American Nuclear Society, 1984-06 |
| An Improved Cost-Benefit Criterion Using Utility Theory Ra, KY; Chang, Soon-Heung, 1984 American Nuclear Society Annual Meeting, pp.523 - 525, American Nuclear Society, 1984 |
| An Integral Approach to Evaluate Containment Heat Transfer Coefficients Choi, JH; Chang, Soon-Heung, 1984 American Nuclear Society Annual Meeting, pp.490 - 491, American Nuclear Society, 1984 |
| Analysis for Design of Passive Safety Injection Line in IPSS Kim, Jihee; Kim, Sang Ho; Chang, Soon-Heung, 2013 한국원자력학회 춘계학술발표회, 한국원자력학회, 2013-05-30 |
| Analysis for Passive Safety Injection of IPSS in Various LOCAs Kim, Sang Ho; Chang, Soon-Heung, 2013 한국원자력학회 춘계학술발표회, 한국원자력학회, 2013-05-30 |
| Analysis of Hydrogen Economy using Vensim Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28 |
| Analysis of Nuclear Battery Using Semiconductor Chang, WJ; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
| Analysis of World Nuclear Market and Strategy of Korean NPP’s Competitiveness Improvement for Exportation Choi, Jae Young; Roh, Seungkook; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27 |
| Analysis on Fission Products Diffusion using Finite Difference Method Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10 |
| Applicability of a nanofluid for a thermal-hydraulic system: Critical heat flux of Al2O3-water nanofluid in a pool boiling Bang, I.C.; Chang, Soon-Heung, International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.5, pp.2935 - 2944, American Nuclear Society, 2005-05-15 |
| Applicability of Nano-fluids for a Thermal Hydraulic System : Boiling Heat Transfer Characteristics of Al2O3 Nano-fluids Bang, IC; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004 |
| Applicability of the quenching mesh under severe accident conditions Hong, S.W.; Song, J.H.; Chang, Soon-Heung, 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1042 - 1050, 2004-06-13 |
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