Showing results 43 to 86 of 86
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 |
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 |
Development of a Computer Code to Estimate the Fuel Rod Failure Using Primary Coolant Activities of Operating PWRs 전문헌, 대한방사선방어학회 99 추계 학술발표회, 1999 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
Influence Diagram Method for Containment Performance Analysis 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Ulsan, pp.549 - 556, 1995 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
Reanalysis of Zion Risk Chun, Moon Hyun, The 15th water Reactor Safety Meeting held at NBS, BNL-NUREG-40831, 1987 |
Reflux Condensation Phenomena in Vertical U-tubes With and Without Noncondensible Gases Chun, Moon Hyun, ASME Paper, 1984 |
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 |
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 |
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 |
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 |
소형관에서의 과냉수 방출에 따른 임계질량유속 예측모델 개발 전문헌, Proc. of the Korean Nuclear Society Spring Meeting, Ulsan, pp.349 - 355, 1995 |
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 |
액체식 태양열 집열기의 열성능 시험장치 설계 전문헌; 차기철; 한세범, 대한기계학회 에너지 및 동력공학부문 학술강연회 초록집, pp.29 - 34, 1982 |
액체식 평판형 집열기를 사용한 자연순환식 급탕시스쳄에 관연한 연구 전문헌, 1985 년도 태양에너지 학술발표회 초록집, pp.5 - 6, 1985 |
액체식 평판형 태양열 집열기의 성능 및 변수에 관한 연구 전문헌, 태양에너지학회 학술발표회 논문초록집, pp.3 - 15, 1983 |
열교환기 성능이 피동잔열제거 계통에 미치는 영향 전문헌; 홍성완; 강명기, Proc. of the Korean Nuclear Society Spring Meeting, Pohang, pp.309 - 315, 1994 |
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 |
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 |
자연순환식 태양열 급탕 시스템의 시뮬레이션 및 성능실험 전문헌, '84 년도 태양에너지 학술강연회, pp.7 - 14, 1984 |
초음파 Rulse-Echo 방법에 의한 액체막 두께 측정 전문헌, 한국원자력학회 제 16 회 정기총회 및 학술발표회 논문초록집, pp.53 - 54, 1983 |
캐파시턴스 변환기를 이용한 유동영역의 결정과 기포율 측정기술에 관한 연구 전문헌, 한국원자력학회 제 16 회 정기총회 및 학술발표회 논문초록집, pp.51 - 52, 1983 |
태양열 주택 및 가정용 온수 시스템의 설계용 전산코드 전문헌, 84 년도 태양에너지 학술강연회 초록집, pp.1 - 4, 1984 |
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