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Study on Visualization and Void-fraction Measurement of Boiling Two-Phase Flow by Using Neutron Radiography

Study on Visualization and Void-fraction Measurement of Boiling Two-Phase Flow by Using Neutron Radiography
中子射线照相沸腾两相流可视化及空隙率测量研究
批准号:
10480118
负责人:
MISHIMA Kaichiro
金额:
$1.98万
依托单位:
依托单位国家:
日本
项目类别:
Grant-in-Aid for Scientific Research (B).
财政年份:
1998
资助国家:
日本
项目状态:
已结题
起止时间:
1998 至 2000

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中文摘要
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英文摘要
The purpose of this study is to investigate flow characteristics (flow regime and void fraction) as a first step of thermal-hydraulic research on boiling two-phase flow in narrow channels. Using neutron radiography with a steady neutron beam, subcooled-boiling two-phase flow in a narrow rectangular channel is visualized and the void fraction is measured.In FY1998, a movable thermal-hydraulic test loop for neutron radiography experiment was set up and the observation of flow regimes and the void fraction was measured for subcooled-boiling in the flow channel. The experiment was performed using the JRR-3M reactor of Japan Atomic Energy Research Institute as a neutron source and the high-frame-rate neutron radiography system as a imaging system. Comparing the experimental results with existing correlations, it turned out that the evaluation of measurement error was very important. For this, in FY1999, the method for void fraction measurement was examined and the measurement error was eval … More uated by inserting a polystyrene sheet in the same flow channel as used in FY1998 to simulate the boiling two-phase flow. Images taken by the high-frame-rate imaging system were processed by an image processing system and the equivalent void fractions of the test section with the polystyrene sheet were obtained by the Σ-scaling method. Then the measurement errors were evaluated for instantaneous and time-averaged void fractions by comparing the measured and theoretical equivalent void fractions. In FY2000, instantaneous and time-averaged void fraction profiles were obtained for boiling two-phase flow in a narrow rectangular channel by using the same method as developed and verified in FY1999, and the flow characteristics were investigated. By analyzing the data, useful information was obtained on the flow regimes near critical heat flux conditions, detailed structure of void fraction distribution in the subcooled-boiling region, and so forth, for boiling two-phase flow in a narrow rectangular channel. Less
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呉田昌俊,日引俊,三島嘉一郎,秋本肇: "中性子ラジオグラフィ高速度撮像法の沸騰流計測への応用(第2報,短加熱長矩形流路内沸騰流の正味の沸騰開始点)"日本機械学会論文集(B編). (掲載予定). (2001)
Masatoshi Kureta、Shun Hiki、Kaichiro Mishima、Hajime Akimoto:“中子射线照相高速成像方法在沸腾流测量中的应用(第二次报告,短加热长矩形通道中沸腾流的净沸腾起始点)”论文集日本机械工程师学会(B 部分)(待出版)。
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呉田昌俊,日引俊,三島嘉一郎,秋本肇: "中性子ラジオグラフィ高速度撮像法の沸騰流計測への応用(第1報、計測誤差評価とボイド率計測)"日本機械学会論文集(B編). 67巻653号(掲載予定). (2001)
Masatoshi Kureta、Shun Hiki、Kaichiro Mishima、Hajime Akimoto:“中子射线照相高速成像方法在沸腾流测量中的应用(第1次报告、测量误差评估和空隙率测量)”日本机械工程学会会议记录(B版) ) )。第 67 卷,第 653 期(待出版)。
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呉田昌俊,日引俊,三島嘉一郎,秋本肇: "中性子ラジオグラフィ高速度撮像法の沸騰流計測への応用(第2報,短加熱長矩形流路内沸騰流の正味の沸騰開始点)"日本機械学会論文集. (掲載予定). (2001)
Masatoshi Kureta、Shun Hiki、Kaichiro Mishima、Hajime Akimoto:“中子射线照相高速成像方法在沸腾流测量中的应用(第二次报告,短加热长矩形通道中沸腾流的净沸腾起始点)”论文集日本机械工程师学会(待出版)(2001 年)。
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T.Hibiki and K.Mishima: "Flow regime transition criteria for upward two-phase flow in vertical narrow rectangular channels"Nuclear Engineering and Design. 203巻. 117-131 (2001)
T.Hibiki 和 K.Mishima:“垂直窄矩形通道中向上两相流的流态转变标准”核工程与设计卷 203. 117-131 (2001)。
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12
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