Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Baek, WP
Showing results 1 to 60 of 60
| A correction method for heated length effect in critical heat flux prediction Lee, YH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.1 - 11, 2000-06 |
| A Digital Photographic Study on Nucleate Boiling in Subcooled Flow Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001 |
| 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 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 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 photographic study on the near-wall bubble behavior in subcooled flow boiling Chang, Soon-Heung; Bang, IC; Baek, WP, INTERNATIONAL JOURNAL OF THERMAL SCIENCES, v.41, no.7, pp.609 - 618, 2002-07 |
| A STUDY OF CRITICAL HEAT-FLUX FOR LOW FLOW OF WATER IN VERTICAL ROUND TUBES UNDER LOW-PRESSURE Chang, Soon-Heung; Baek, WP; Bae, TM, NUCLEAR ENGINEERING AND DESIGN, v.132, no.2, pp.225 - 237, 1991-12 |
| 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 improved physical model for flooding limited CHF under zero and very low flow conditions Park, C; Hwang, DH; Chang, Soon-Heung; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.25, no.3, pp.339 - 348, 1998-04 |
| An independent assessment of Groeneveld et al.s 1995 CHF look-up table Baek, WP; Kim, HC; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.178, no.3, pp.331 - 337, 1997-12 |
| An integral equation model for critical heat flux at subcooled and low quality flow boiling Chun, TH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.13 - 29, 2000-06 |
| Assessment of a tube-based bundle CHF prediction method using a subchannel code Chun, TH; Hwang, DH; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.25, no.14, pp.1159 - 1168, 1998-09 |
| Assessment of CHF correlations for internally heated concentric annulus channels Park, JW; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.8, pp.1077 - 1086, 1996-12 |
| Assessment of passive containment cooling concepts for advanced pressurized water reactors Lee, SW; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.24, no.6, pp.467 - 475, 1997-04 |
| CHF detection using spationtemporal neural network and wavelet transform Kim, SH; Bang, IC; Baek, WP; Chang, Soon-Heung; Moon, SK, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.27, no.2, pp.285 - 292, 2000-02 |
| CHF mechanism for pool boiling of R-113 on a horizontal heater No, Hee Cheon; Chung, HJ; Chun, SY; Kim, BD; Baek, WP, NURETH10, 2003 |
| 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 |
| 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 |
| Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow Park, C; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.4, pp.453 - 464, 1997 |
| Critical heat flux and flow pattern for water flow in annular geometry Park, JW; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.172, no.1-2, pp.137 - 155, 1997 |
| Critical heat flux experiments on the reactor vessel wall using 2-D slice test section Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11 |
| Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions Park, C; Chang, Soon-Heung; Baek, WP, NUCLEAR ENGINEERING AND DESIGN, v.183, no.3, pp.235 - 247, 1998-07 |
| 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 Kim, HC; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.49 - 73, 2000-06 |
| 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 |
| Critical heat flux prediction using genetic programming for water flow in vertical round tubes Lee, DG; Kim, HG; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.7, pp.919 - 929, 1997 |
| Critical heat flux under flow oscillation of a water at low-pressure, low-flow conditions Kim, YI; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.193, no.1-2, pp.131 - 143, 1999-09 |
| Derivation of mechanistic critical heat flux model for water based on flow instabilities Chang, Soon-Heung; Kim, YI; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.8, pp.1109 - 1119, 1996-12 |
| 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 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 |
| Direct observation of a liquid film under a vapor environment in a pool boiling using a nanofluid Bang, IC; Chang, Soon-Heung; Baek, WP, APPLIED PHYSICS LETTERS, v.86, no.13, pp.382 - 388, 2005-03 |
| Effects of Surface Inclination Angle and Size on Critical Heat Flux Yang, SH; Baek, WP; Chang, Soon-Heung, '97 ANS Winter Meeting, ANS, 1997 |
| Effects of the spacer and mixing vanes on critical heat flux for low-pressure water at low-velocities Chung, JB; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.6, pp.757 - 765, 1996-10 |
| Experimental study of critical heat flux for low flow of water in vertical round tubes under low pressure Baek, WP; Park, JW; Chang, Soon-Heung, Winter Annual Meeting of the American Society of Mechanical Engineers, v.220, pp.35 - 43, American Society of Mechanical Engineers, 1992-11-08 |
| Experimental Sutdy and Correlation Development of Critical Heat Flux Under Low Pressure and Low Flow condition Kim, HC; Baek, WP; Kim, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997 |
| 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 |
| Future Light Water Reactor Development Programs in Korea Baek, WP; Chang, Soon-Heung, Tht 2nd Japan-Korea Seminar on Advanced Reactors, 1996 |
| Hybrid accident simulation methodology using artificial neural networks for nuclear power plants Choi, YJ; Kim, HK; Baek, WP; Chang, Soon-Heung, INFORMATION SCIENCES, v.160, no.1-4, pp.207 - 224, 2004-03 |
| Improved methodology for generation of axial flux shapes in digital core protection systems Lee, GC; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.29, no.7, pp.805 - 819, 2002-05 |
| 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 |
| Korea looks beyond the next generation Chang, Soon-Heung; No, Hee Cheon; Baek, WP; Lee, SI; Lee, SW, NUCLEAR ENGINEERING INTERNATIONAL, v.42, no.511, pp.12 - 12, 1997-02 |
| Measurement of critical heat flux for narrow annuli submerged in saturated water Kim, SH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.41 - 48, 2000-06 |
| 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, WP; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.45, no.19, pp.3987 - 3996, 2002-09 |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - part 1 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.1, pp.1 - 1, 2005-10 |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - Part 2 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.2, pp.143 - 143, 2005-11 |
| Nuclear Safety and Public Acceptance Baek, WP; Chang, Soon-Heung, The 7th Nuclear Energy Symposium (NES-7), 2002 |
| Parametric trends analysis of the critical heat flux based on artificial neural networks Moon, SK; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.163, no.1-2, pp.29 - 49, 1996-06 |
| 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 |
| Pool-boiling critical heat flux of water on small plates: Effects of surface orientation and size Yang, SH; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.8, pp.1093 - 1102, 1997-12 |
| 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 |
| Review on Visualization Results of DNB and Relations with Hypertheses of DNB Models Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2003 |
| 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 |
| Visualization of a principle mechanism of critical heat flux in pool boiling Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12 |
| Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363, 2004-09 |
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