NE-Conference Papers(학술회의논문)

Recent Items

Collection's Items (Sorted by Submit Date in Descending order): 5321 to 5340 of 5619

5321
Development of a Compact Real-Time Simulator for Two-Loop PWR Plant, FISA-2/PC

No, Hee Cheon; Jeong, Jae Jun, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations , 1988

5322
Three-Dimensional Two-Fluid Code for U-Tube Steam Generator Thermal Design Analysis

No, Hee Cheon; Lee, Jae Young, Second Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1986

5323
Classification of Critical Heat Flux Patterns Based on Parametric Trends Using the Entropy Minimax Principle

Baek, WP; Park, JW; Chang, Soon-Heung, International Conference on Multiphase Flow, pp.67 - 70, 1991

5324
Conceptual Design of an Inherently Safe and Simple Tube Reactor Using Water as Moderator and Coolant

Baek, WP; Chang, Soon-Heung, IAEA Tech. Committee Meeting on Progress in Devel. & Design Aspects of Water-Cooled Reactors, 1991

5325
Development of an Expert System for Malfuction Diagnosis of Primary System in Nuclear Power Plant

Chung, HY; Park, IS; Hur, SK; Cheon, SW; Kim, HG; Chang, Soon-Heung, The 3rd Symposium on Expert Systems Application to Power Systems, pp.539 - 547, 1991-04

5326
Effect of Strain Aging on the Deformation Behavior in SA508-Cl.3 Nuclear Pressure Vessel

김인섭, Fall Meeting of Korean Nuclear Society, 1989

5327
Derivation of Yield Stress in Beta-Transformed Zircaloy-4 Nuclear Fuel Sheaths

김인섭, Spring Meeting of Korean Nuclear Society, 1988

5328
Effects of Texture and Microstructure on the Mechanical Properties of Heat-Treated Zircaloy-4

Kim, In Sup, Second International Conference on Candu Fuel, Chalk River, Canada, pp.1 - 5, 1989

5329
A Study on the Microscopic Fracture Characteristics of A 533B-1 Nucler Pressure Vessel Steels

Kim, In Sup, International Symposium on Pressure Vessel Technology, Seoul, Korea, pp.19 - 21, 1989

5330
Effect of Microstructure on the Ductile Fracture of Ferrite-Martensite-Bainite Steels

Kim, In Sup, Fall Meeting of TMS-AIME, Chicago, U.S.A., 1988

5331
Changes of the Texture and Anisotropic Mechanical Properties in Zircaloy-4 Fuel Cladding due to the Effect of B-Heat Treatment

Kim, In Sup, Fall Meeting of the Atomic Energy Society of Japan, 1987

5332
Korean Experiences in Developing Nuclear Power Programme

Byong-Whi Lee, Senior Expert Group Meeting, pp.1 - 3, 1986

5333
Physical Modeling and Finite Element Method for the Analysis of Lateral Phase Distribution Phenomena

Lee, GJ; Chang, Soon-Heung, International Conference on Multiphase Flow, Tsukuba, 1991

5334
Prediction of Nuclear Reactor Parameters Using Artificial Neural Network Models

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

5335
Mechanistic Flux Model of the Inverted Annular Film Boiling

Ho, S.; Chang, Soon-Heung, The 9th International Heat Transfer Conference, pp.431 - 436, 1990

5336
A Refined Mechanistic Critical Heat Flux Model for Upflow Boiling at Low Qualities

Lee, KW; Chang, Soon-Heung, The 9th International Heat Transfer Conference, Jerusalem, pp.141 - 146, 1990

5337
Time Dependent Analysis of Quenching Phemonenon with the Nonuniformity of Water Penetration Pattern in Hot Debris Bed

Lee, KW; Chang, Soon-Heung, The 2nd International Topical Meeting on Nucl. Power Plant Ther. Hydrau. and Operation, pp.26 - 33, 1986-04

5338
A Phenomenological Modeling for the High Pressure Melt Ejection from a Reactor Cavity

전문헌, 한국원자력학회 '90 춘계학술발표회 논문집 (I), pp.609 - 619, 1990

5339
Analysis of Melting at the Wall in Laminar Flowin a Cylindrical Channel

전문헌, 한국원자력학회 '93 춘계학술발표회 논문집 (I), pp.383 - 394, 1990

5340
A Large Dry PWR Containment Response Analysis for Postulated Severe Accidents

전문헌, 한국원자력학회 '87 춘계학술발표회, pp.30 - 31, 1987

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