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

Showing results 44 to 86 of 86

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

61
Interfacial Condensation Heat Transfer for Countercurrent Steam-Water Stratified Flow in a Circular Pipe

Chun, Moon Hyun, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9), 1999

62
Interfacial Condensation Heat Transfer for Countercurrent Steam-Water Stratified Flow in a Horizontal Circular Pipe

Chun, Moon Hyun, Proc. of NTHAS98 (Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, pp.299 - 306, 1998

63
Methodology for Estimating the Number of Failed Fuel Rods in Operating PWRs Using Diffusion and Kinetic Models

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Taejon, pp.97 - 102, 1996

64
Natural convection heat transfer correlation for laminar and turbulent film condensation on a vertical surface

Chun, Moon Hyun; Kim Kyun-Tae, Proceedings of the 3rd ASME/JSME Thermal Engineering Joint Conference Part 2 (of 5), pp.459 - 464, 1991-03-17

65
Numerical Analyses for Reflood Simulation Based on a Mechanistic, Best-Estimate Approach by KREWET Code

Chun, Moon Hyun, Proc. of the International Conference on Numerical Methods in Nuclear Engineering, Montreal, Quebec, pp.513 - 529, 1983

66
Onset of Slugging Criterion Based on Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations of Two-Fluid Model

Chun, Moon Hyun, Proc. of the FIFTH International Topical Meeting on Nuclear Thermal Hydraulic, Operations, & Safety (NUTHOS-5)6, 1997

67
Parametric Effects of Ambient Conditions on Thermal Safety of Wolsung (CANDU) Unit 1 Spent Fuel Dry Storage Canister

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.527 - 533, 1992

68
Predition of the Onset of Slug Flow in Nearly Horizontal Air-Water Countercurrent Flow

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, pp.368 - 373, 1997

69
Reanalysis of Zion Risk

Chun, Moon Hyun, The 15th water Reactor Safety Meeting held at NBS, BNL-NUREG-40831, 1987

70
Reflux Condensation Phenomena in Vertical U-tubes With and Without Noncondensible Gases

Chun, Moon Hyun, ASME Paper, 1984

71
Simple Measure of Uncertainty Importance Using Entire Change of Cumulative Distribution Functions

Chun, Moon Hyun, Proc. of the International Topical Meeting on Probabilistic Safety Assessment (PSA99), pp.269 - 278, 1999

72
The Fuzzy Set Theory Application to the Analysis of Accident Progression Event Trees with Phenomenological Uncertainty Issues

Chun, Moon Hyun, Proc. of the 1st JSME/ASME Joint International Conference On Nuclear Engineering, pp.383 - 391, 1991

73
Thermal Analysis of Wolsung Unit 1 (CANDU) Spent Fuel Dry Storage Canister

Chun, Moon Hyun, 16th Biennial ANS Topical Meeting on Reactor Operations Experience, pp.98 - 104, 1993

74
Wire Spacer 형상이 압력강하에 미치는 영향에 관한 실험적 연구 (An Experimental Investigation of Wire Spacer Geometry Effects on Pressure Drop)

전문헌, 한국원자력학회 99 추계학술발표회, 1999

75
소형관에서의 과냉수 방출에 따른 임계질량유속 예측모델 개발

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Ulsan, pp.349 - 355, 1995

76
수직관 벽면을 통한 열유속 측정 및 보정 방법 (A Measurement and Compensation Method of the Heat Flux through a Vertical Tube Wall)

전문헌, 한국원자력학회 99 추계학술발표회, 1999

77
액체식 태양열 집열기의 열성능 시험장치 설계

전문헌; 차기철; 한세범, 대한기계학회 에너지 및 동력공학부문 학술강연회 초록집, pp.29 - 34, 1982

78
액체식 평판형 집열기를 사용한 자연순환식 급탕시스쳄에 관연한 연구

전문헌, 1985 년도 태양에너지 학술발표회 초록집, pp.5 - 6, 1985

79
액체식 평판형 태양열 집열기의 성능 및 변수에 관한 연구

전문헌, 태양에너지학회 학술발표회 논문초록집, pp.3 - 15, 1983

80
열교환기 성능이 피동잔열제거 계통에 미치는 영향

전문헌; 홍성완; 강명기, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.309 - 315, 1994

81
열교환기 튜브 구조가 열전달과 탱크 내부 온도에 미치는 영향에 대한 실험적 연구

전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.379 - 384, 1994

82
열교환기 튜브 조건이 비등 열전달에 미치는 영향에 대한 실험적 연구

전문헌, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, Korea, pp.257 - 264, 1994

83
자연순환식 태양열 급탕 시스템의 시뮬레이션 및 성능실험

전문헌, '84 년도 태양에너지 학술강연회, pp.7 - 14, 1984

84
초음파 Rulse-Echo 방법에 의한 액체막 두께 측정

전문헌, 한국원자력학회 제 16 회 정기총회 및 학술발표회 논문초록집, pp.53 - 54, 1983

85
캐파시턴스 변환기를 이용한 유동영역의 결정과 기포율 측정기술에 관한 연구

전문헌, 한국원자력학회 제 16 회 정기총회 및 학술발표회 논문초록집, pp.51 - 52, 1983

86
태양열 주택 및 가정용 온수 시스템의 설계용 전산코드

전문헌, 84 년도 태양에너지 학술강연회 초록집, pp.1 - 4, 1984

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