ICONE11-36062 A STUDY ON THE CHARACTERISTICS OF UPWARD AIR-WATER TWO-PHASE FLOW ALONG A LARGE PIPE
スポンサーリンク
概要
著者
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MISHIMA Kaichiro
Research Reactor Institute, Kyoto University
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Mishima Kaichiro
Research Reactor Institute Kyoto University
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SHEN Xiuzhong
Research Reactor Institute, Kyoto University
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NAKAMURA Hideo
Tokai Establishment, Japan Atomic Energy Research Institute
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Shen Xiuzhong
Research Reactor Institute Kyoto University
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Nakamura Hideo
Tokai Establishment Japan Atomic Energy Research Institute
関連論文
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- ICONE11-36062 A STUDY ON THE CHARACTERISTICS OF UPWARD AIR-WATER TWO-PHASE FLOW ALONG A LARGE PIPE
- E110 EVALUATION OF CRITICAL HEAT FLUX FOR LATERALLY HALF-HEATED TUBE USING RIVULET FORMATION MODEL(Critical heat flux)
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- Application of Neutron Radiography to Visualization and Void Fraction Measurement of Air-Water Two-Phase Flow in a Small Diameter Tube.