ICONE11-36263 INTERFACIAL STRUCTURES IN DOWNWARD TWO-PHASE BUBBLY FLOW
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概要
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Downward two-phase flow was studied considering its significance in view of Light Water Reactor Accidents (LWR) such as Loss of Heat Sink (LOHS) by feed water loss or secondary pipe break. The flow studied, was an adiabatic, air-water, co-current, vertically downward two-phase flow. The experimental test sections had internal hydraulic diameters of 25.4 mm and 50.8 mm. Flow regime map was obtained using the characteristic signals obtained from an impedance void meter, employing neural network based identification methodology to minimize the subjective judgment in determining the flow regimes. A four sensor conductivity probe was used to measure the local two phase flow parameters, which characterize the interfacial structures. The local time averaged two-local two phase flow parameters, which characterize the interfacial structures. The local time averaged two-phase flow parameters measured were : void fraction (α), interfacial area concentration (a_i), bubble velocity (v_g), and Sauter mean diameter (D_sm). The flow conditions were from the bubbly flow regime. The local profiles of these parameters as well as their axial development revealed the nature of the interfacial structures and the bubble interaction mechanisms occurring in the flow. Furthermore, this study provided a good database for the development of the interfacial area transport equation, which dynamically models the changes in the interfacial area along the flow field. An interfacial area transport equation was developed for downward flow based on that developed for the upward flow, with certain modifications in the bubble interaction terms. The area averaged values of the interfacial area concentration were compared with those predicted by the interfacial area transport model. In most of the bubbly flow conditions the one-group interfacial area transport model worked resonably well.
- 一般社団法人日本機械学会の論文
著者
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Ishii Mamoru
Thermal-hydraulics And Reactor Safety Laboratory School Of Nuclear Engineering Purdue University
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Paranjape Sidharth
Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering, Purdue University
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Kim Seungjin
Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering, Purdue University
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Kelly Joseph
U. S. Nuclear Regulatory Commission
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Kim Seungjin
Thermal-hydraulics And Reactor Safety Laboratory School Of Nuclear Engineering Purdue University
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Paranjape Sidharth
Thermal-hydraulics And Reactor Safety Laboratory School Of Nuclear Engineering Purdue University
関連論文
- ICONE11-36263 INTERFACIAL STRUCTURES IN DOWNWARD TWO-PHASE BUBBLY FLOW
- ICONE11-36115 DEVELOPMENT OF TWO-GROUP INTERFACIAL AREA TRANSPORT EQUATION FOR CONFINED FLOW-II : MODEL EVALUATION
- ICONE11-36114 DEVELOPMENT OF TWO-GROUP INTERFACIAL AREA TRANSPORT EQUATION FOR CONFINED FLOW-I : MODELING OF BUBBLE INTERACTIONS