1 | A Combined Procedure of RSM and LHS for Uncertainty Analyses in Source Term Quantifications Using MAAP3.0B Code Chun, Moon Hyun, Proc. of the International Topical Meeting on Probabilistic Safety Assessment (PSA'96), pp.325 - 332, 1996 |
2 | A Correlation for Critical Pressure with Subcooled Upstream Conditions 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.357 - 370, 1990 |
3 | A Criterion for the Onset of Slugging in Horizontal Stratified Air-Water Countercurrent Flow Chun, Moon Hyun, Proc. of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics. (NURETH-7), pp.93 - 110, 1995 |
4 | A Critical Review of the Current PWR Containment Response Analysis Methodologies for Postulated Severe Accident Chun, Moon Hyun, Proc. of Third Int'l. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins. (NUPTHO-3), 1988 |
5 | A Friction Factor Correlation for a Rod Bundle with a Helical Wire Spacer Chun, Moon Hyun, ExHFT-5 (5th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, T, 2001 |
6 | A Guide Map for Lower and Upper Boundary Regions to Avoid the Condensation-Induced Water Hammer in a Long Horizontal Pipe 전문헌, Korean Nuclear Society Autumn Meeting, pp.305 - 311, 1994 |
7 | A Large Dry PWR Containment Response Analysis for Postulated Severe Accidents 전문헌, 한국원자력학회 '87 춘계학술발표회, pp.30 - 31, 1987 |
8 | A Natural Convection Heat Transfer Correlation for Laminar and Turbulent Film Condensation on a Vertical Surface Chun, Moon Hyun, 3rd ASME/JSME Thermal Engineering Joint Conference, pp.459 - 464, 1991 |
9 | A New Correlation for Two-Phase Critical Discharge Coefficient 전문헌, 한국원자력학회 '89 춘계학술발표회 논문집, pp.123 - 132, 1989 |
10 | A New Measure of Uncertainty Importance Based on Distributional Sensitivity Analysis for PSA 전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.415 - 420, 1996 |
11 | A New Method of Two-Phase Pressure Drop Calculation with a Correction Factor to Compensate Expected Errors Chun, Moon Hyun, Proc.of the Third Int'l. Topical Meeting on Nucl. Power Plant Thermal Hydraulics and Operation. (NUPTHO-3), 1988 |
12 | A New Transition Criterion for Stratified and Nonstratified Flow in Pipes 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Cheju, pp.219 - 226, 1996 |
13 | A Numerical Model for Analyses of Reflooding Phase of LOCA Chun, Moon Hyun, ASME Paper No.82-WA/HT-32, 1982 |
14 | A Parametric Study of Air-Water Countercurrent Flow Limitation in a Horizontal Pipe Connected to an Inclined Riser 전문헌, Korean Nuclear Society Spring Meeting, 1999 |
15 | A Parametric Study of Condensation-Induced Water Hammer in Nuclear Power Plants 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.463 - 477, 1990 |
16 | A Parametric Study of the High Pressure Melt Ejection from Two Different Scale Reactor Cavity Models 전문헌, Proc. of the 13th KAIF-JAIF Seminar on Nuclear Industry, pp.337 - 346, 1991 |
17 | A Phenomenological Modeling for the High Pressure Melt Ejection from a Reactor Cavity 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.609 - 619, 1990 |
18 | A Semi-Empirical Correlation for an Adiabatic Interfacial Friction Factor 전문헌, Proc. of Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.29 - 34, 1993 |
19 | A Simplified Computational Scheme for Thermal Analysis of LWR Spent Fuel Dry Storage and Transportation Cask 전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, pp.323 - 329, 1997 |
20 | A Study on the AP600 Passive Residual Heat Removal System 전문헌, The 10th KAIF/KNS Annual Conference Seoul, Korea, 1995 |
21 | A Theoretical and Experimental Study of the Steam Condensation Effect on the CCFL in Nearly Horizontal Two-Phase Flow 전문헌, 대한기계학회 1999년도 열공학부문 추계학술대회, pp.515 - 523, 1999 |
22 | A Two-Phase Pressure Drop Calculation Code Based on a New Method with a Correction Factor Obtained from an Assessment of Existing Correlations Chun, Moon Hyun, Proc. of Condensde Papers of the 5th Miami Int'l Sysposium on Muliti-phase Transport and Particulate Phenomena, 1988 |
23 | An Experimental and Theoretical Investigation of the Criterion for Transition to Slug Flow in Horizontal Countercurrent Stratified Wavy Flow 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.427 - 434, 1994 |
24 | An experimental investigation of reflux condensation phenomena in multiple U-tubes with and without noncondensible gas Chun, Moon Hyun; Lee K.-W.; Chu I.-C., 2001 ASME International Mechanical Engineering Congress and Exposition, v.369, no.2, pp.99 - 109, 2001-11-11 |
25 | An Experimental Investigation of Reflux Condensation Phenomena in Vertical U-tubes with and without a Noncondensible Gas 전문헌, 한국원자력학회 춘계학술발표회, pp.14 - 16, 1984 |
26 | An Experimental Investigation of Side-Orifice Effects on Pressure Drop for Single-Phase Flow 전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.295 - 300, 1996 |
27 | An Experimental Investigation of the Adiabatic Interfacial Friction Factor in Horizontal Air-Water Countercurrent Stratified Flow Chun, Moon Hyun, Sysmposium on Transient Thermal Hydraulics, Heat Transfer, Fluid-Structure Interaction, and Sfructure Dynamics P.V.P, pp.1 - 9, 1994 |
28 | An Experimental Investigation of the Interfacial Condensation Heat Transfer in Steam/Water Countercurrent Stratified Flow in a Horizontal Pipe 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, pp.565 - 570, 1998 |
29 | An experimental study of liquid entrainment by rapid surface swelling of two-phase mixture in a vessel Chun, Moon Hyun; Seo K.-W.; Kim H.-K., 2001 ASME International Mechanical Engineering Congress and Exposition, v.369, no.2, pp.291 - 296, 2001-11-11 |
30 | An Experimental Study of the High Pressure Melt Ejection from a Reactor Vessel 전문헌, 한국원자력학회 '90 춘계학술 발표회 논문집(1), pp.597 - 607, 1990 |
31 | An Experimental Study of the Interfacial Friction Factor for Countercurrent Stratified Air-Water Flow in Nearly Horizontal and Inclined Pipes 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Cheju, pp.247 - 253, 1996 |
32 | An Extension of the Slug Flow Transition Model to Include the Steam Condensation Effect on CCFL 전문헌, Proc. of International Conference on Nuclear Engineering, pp.1 - 10, 2000 |
33 | An Iterative Uncertainty Analysis for Assessment of Large Computer Codes 전문헌, 한국원자력학회 제 18 회 정기총회 및 학술발표회 논문초록집, pp.52 - 53, 1985 |
34 | Analyses of Reliability for a Typical Solar Heating System Chun, Moon Hyun, Proc. of the ASME Solar Energy Division Fifth Annual Conference Orlando, pp.506 - 511, 1983 |
35 | Analysis of Event Tree with Imprecise Inputs by Fuzzy Set Theory 전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (II), pp.783 - 794, 1990 |
36 | Analysis of Forced Convection Melting in a Vertical Channel for Applications to LMFBRs Post-Accident Fuel Relocation Chun, Moon Hyun, Proc. of the Third International Topical Meeting on Reactor Thermal Hydraulics Newport, Rhode Island, 1985 |
37 | Analysis of Melting at the Wall in Laminar Flowin a Cylindrical Channel 전문헌, 한국원자력학회 '93 춘계학술발표회 논문집 (I), pp.383 - 394, 1990 |
38 | Analysis of Melting Phenomena of a Circular Tube Geometry for Applications in an HCDA of an LMFBR 전문헌, 한국원자력학회 춘계학술발표회 논문초록집, pp.25 - 27, 1984 |
39 | Analytical Models for Lower and Upper Bounds of the Condensation-Induced Waterhammer in Long Horizontal Pipes 전문헌, Korean Nuclear Society Spring Meeting, pp.101 - 107, 1992 |
40 | Assessment of the New and Existing Correlations for Laminar and Turbulent Film Condensations on a Vertical Surface 전문헌, 한국원자력학회 ' 90 춘계학술발표회, pp.371 - 382, 1990 |
41 | Assessment of Two Uncertainty Quantification Methods for Source Term Analysis 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.497 - 502, 1994 |
42 | Average Liquid Level and Pressure Drop for Countercurrent Stratified Two-Phase Flow 전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.301 - 306, 1996 |
43 | Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters Chun, Moon Hyun, Proc. of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), pp.759 - 766, 1997 |
44 | Development of a Computer Code to Estimate the Fuel Rod Failure Using Primary Coolant Activities of Operating PWRs Chun, Moon Hyun, Proc. of the ASME 6th International Conference on Nuclear Engineering (ICONE-6), 1998 |
45 | Development of a Computer Code to Estimate the Fuel Rod Failure Using Primary Coolant Activities of Operating PWRs 전문헌, 대한방사선방어학회 99 추계 학술발표회, 1999 |
46 | Effect of Initial Liquid Level on the Countercurrent Flow Limitation in a Horizontal Pipe Connected to an Inclined Riser Chun, Moon Hyun, Proc. of NTHAS-2000 (Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2000 |
47 | Effects of Gap Resistance and Failure Location on Prompt Fission Gas Release from a Cladding Breach 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, pp.184 - 189, 1997 |
48 | Effects of heat exchanger tube parameters on nucleate pool boiling heat transfer in a scaled IRWST Chun, Moon Hyun; Kang Myeong-Gie, Proceedings of the 1996 4th ASME/JSME International Conference on Nuclear Engineering, ICONE-4. Part 4 (of 5), v.1, pp.853 - 866, 1996-03-10 |
49 | Effects of Interfacial Shear Between the Gas and Turbulent Falling Liquid Film on Heat Transfer Coefficient 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.317 - 323, 1994 |
50 | Effects of the Entrance Shape of Sudden Contraction on Single and Two-Phase Pressure Drop in a Horizontal Air-Water Flow Chun, Moon Hyun, Proc. of Third Int.l. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins, Seoul, 1988 |
51 | Evaluation Method for the Number of Failed Fuel Rods Based on the Dependency of the Fission Product Release on the Defect Size 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Kori, Korea, pp.503 - 510, 1992 |
52 | Experimental investigation of flooding in air-water counter-current flow with a vertical adiabatic multi-rod bundle Chun, Moon Hyun; Chung Bub-Dong; Cha Jong-Hee, ASHE Winter Annual Meeting of the American Society of Mechanical Engineers, 1990, v.99, pp.237 - 242, 1990-11-25 |
53 | Experimental Investigation of Flooding in Air-Water Counter-Current Flow with a Vertical Adiabatic Multi-Rod Bundle 전문헌, Proceedings of the 14th KAIF-JAIF Seminar on Nuclear Industry, pp.225 - 248, 1991 |
54 | Experimental Investigation of Solidification of an Initially Stagnant Fluid on the Outside Wall of a Cooled Channel 전문헌, 한국원자력학회 제 18 회 정기총회 및 학술발표회 논문초록집, pp.65 - 66, 1985 |
55 | Experimental investigation of the adiabatic interfacial friction factor in horizontal air-water countercurrent stratified flow Chun, Moon Hyun; Nam Ho-Yun, Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 1 (of 19), v.270, pp.1 - 9, 1994-06-19 |
56 | Experimental Investigation of the Three Modes of Reflux Condensation and Their Transition Criteria 전문헌, 한국원자력학회 제 17 회 정기총회 및 학술발표회 논문초록집, pp.64 - 65, 1984 |
57 | Flow Regime Characterization and Void Fraction Measurement by Capacitance Transducers Chun, Moon Hyun; Sung Chang-Kyung, Winter Annual Meeting of the American Society of Mechanical Engineers., 1984 |
58 | Heat Removal Capability of the Passive Residual Heat Removal System, Proc. of Passive Safety Features in Nuclear Installations Chun, Moon Hyun, Post-SMIRT 14 International Seminar 18, 1997 |
59 | Influence Diagram Method for Containment Performance Analysis 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Ulsan, pp.549 - 556, 1995 |
60 | Interfacial Condensation for Countercurrent Steam-Water Stratified Smooth/Wavy Flow in a Horizontal Pipe Chun, Moon Hyun, Proc. of NTHAS-2000 (Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2000 |