Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 157

Showing results 1 to 60 of 86

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

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