NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5341 to 5360 of 5619

5341
A New Correlation for Two-Phase Critical Discharge Coefficient

전문헌, 한국원자력학회 '89 춘계학술발표회 논문집, pp.123 - 132, 1989

5342
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

5343
Dynamic Characteristics of a Charcoal Bed for Multi-Component Fission Gases

Lee, Kun Jai, Waste Management '89, pp.619 - 623, 1989

5344
A Simplified Model for the Dynamics of Multi-Component Ion Exchange System

Lee, Kun Jai, SPECTRUM '88 Int'l Topical Meeting on Nuclear and Hazardous Waste Management, pp.11 - 15, 1988

5345
The Solubility of Magnetite and Nickel Ferrite in Aqueous Solutions

Lee, Kun Jai, 1988 JAIF Int'l Conference on Water Chemistry in Nuclear Power Plants, pp.744 - 749, 1988

5346
Emission Rate Measurement of a Cf-252 Neutron Source by Manganeous Sulfate Bath Method

Lee, Kun Jai, Seventh Int'l Congress of the Int'l Radiation Protection Association, pp.10 - 16, 1988

5347
Long-Term Prediction of Radionuclide Leaching from Waste Matrix by Finite-Slab Approximation Method

Lee, Kun Jai, ANS Int'l Topical Meeting on Waste Management, Decontamination and Decommissioning, pp.14 - 18, 1986

5348
Research on Artificial Neural network Applications for Nuclear Power Plant

Cheon, SW; Chang, Soon-Heung, '92 Conference Seminar on Human Cognitive and Cooperation Activities in Adv. Tech., 1992

5349
Proposed Concept of a Passive Water Cooled Reactor without Emergency Core Cooling System

Baek, WP; Lee, GJ; Lee, JY; Chang, Soon-Heung, '92 International Conference on Design and Safety of Advanced Nuclear Power Plant, pp.1 - 6, 1992-10

5350
Expert System for Nuclear Power Plant Performance Evaluation and Diagnosis

Kang, KS; Cheon, SW; Chang, Soon-Heung, IEEE Fifth Conference on Human Factors and Power Plants, IEEE, 1992-06

5351
Application of Neural Networks to Connectionist Expert System for Identification of Transients in Nuclear Power Plants

Cheon, SW; Kang, GS; Roh, MS; Chang, Soon-Heung, The 2nd International Forum on the Expert Systems and Computer Simulation in Energy Eng., 1992-03

5352
An Iterative Uncertainty Analysis for Assessment of Large Computer Codes

전문헌, 한국원자력학회 제 18 회 정기총회 및 학술발표회 논문초록집, pp.52 - 53, 1985

5353
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

5354
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

5355
액체식 평판형 태양열 집열기의 성능 및 변수에 관한 연구

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

5356
초음파 Rulse-Echo 방법에 의한 액체막 두께 측정

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

5357
캐파시턴스 변환기를 이용한 유동영역의 결정과 기포율 측정기술에 관한 연구

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

5358
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

5359
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

5360
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

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