NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5181 to 5200 of 5619

5181
An Experimental Study of the High Pressure Melt Ejection from a Reactor Vessel

전문헌, 한국원자력학회 '90 춘계학술 발표회 논문집(1), pp.597 - 607, 1990

5182
Chernobyl : Nonlinear Reactor Analysis Revisited

Cho, Nam-Zin, Special Lecture, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10

5183
A Mass Conservative Numerical Solution of Vertical Water Flow and Mass Transport Equations in Unsaturated Porous Media

Lee, Kun Jai, 1993 International Conference on Nuclear Waste Management and Environment Remediation, pp.525 - 531, 1993

5184
Effects of Inter-Assembly Spectral Interaction in MOX Cores Analyzed by CASMO-3M/AFEN

Cho, Nam-Zin; Jo, C.K., Proc. of the Korean Nuclear Society Spring Meeting, pp.23 - 28, 1994-05

5185
Desingn of Model Reference Adaptive Control System for Steam Genrators

No, Hee Cheon; Na, Man Gyun, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins, 1988

5186
A Single Continuum Approximation of the Solute Transporet in Fractured Porous Media

Lee, Kun Jai, SPECTRUM '92 Proc. of the International Topical Meeting on Nuclear and Hazardous Waste Management, pp.1540 - 1545, 1992

5187
A Proposed Concept of Passive Pressurized Water Reactor Based on Existing Reactor Coolant System Design

Chang, S.H; Baek, W.P; Lee, S.W; No, H.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.431 - 436, 1992-10

5188
Infinite-Dimensional Observer Theory for Dynamic Estimation of Neutron Flux and Xenon Distributions

Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.131 - 136, 1991-10

5189
Feect of Temperature Strain and Atmosphere on the Low Cycle Fatigue Behavior of ASME SA508cl.3 Forging Steel

김인섭, Proc. of the Seventh Conference on Mechanical Behavior of Materials, 1993

5190
Dynamic Strain-Aging and Fracture Characteristics of Power Plant Components-Carbon Steels and Austenite Alloys

김인섭, Proc. of the Seventh Conference on Mechanical Behavior of Materials, 1993

5191
Analytical and Experimental Studies of U-Tube Steam Generator in PWR in Natural Circulation, Pot-Boiling, and Tube-Uncovery Modes

No, Hee Cheon; Sul, Y.S., International Conference on New Trends in Nuclear System Thermohydraulics, 1994

5192
Stepwise Integral Scaling Method for Severe Accident analysis and its Application to Corium Dispersion in Direct Containment Heating

No, Hee Cheon; Ishii, M.; Zhang, G, Sixth International Topical Mtg on Nuclear Reactor Thermal Hydraulics, 1993

5193
Hyperbolicity Breaking and The Effects of Entrance and Exit Geometry on Flooding

No, Hee Cheon; Jeong, Ji Hwan; Lee, Jae Young, 1993 International Heat Transfer Conference, 1993

5194
Quantitative Evaluation of Reverse Dynamic Effects in steam Generators Using Spectrum Analysis

No, Hee Cheon; Na, Man Gyun, 한국원자력학회 춘계발표회, pp.403 - 408, 한국원자력학회, 1993

5195
Nuclear Power Plant Pressurizer Fault Diagnosis Using fuzzy Signed Diagraph Method

Park, Joo Hyun; Seong, Poong-Hyun, International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety, 1994-04

5196
Supercomputing with Parallel Computers in Reactor Analysis

Cho, Nam-Zin; Kim, Y.H; Song, J.S, Proc. of the 7th KAIF/KNS Annual Conference, pp.465 - 472, 1992-04

5197
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

5198
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

5199
Novel Current Drive Experiments on the CDX-U, HIT, and DIII-D Tokamaks

Ono, M; Forest, CB; Hwang, YS; Armstrong, RJ; Choe, Wonho; Darrow, DS; Jones, T, IAEA International Conference on Plasma Physics and Controlled Nuclear Fusion Research, pp.693 - 700, 1992

5200
Analytical Sensitivity Analysis of the One-Dimensional Solute Transport Equation

이건재, 한국원자력학회 학술발표회 ( 추계 ), pp.231 - 246, 1988

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