Critical Heat Flux Prediction Method Based on Two-Phase Turbulence Model
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概要
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In this paper, we present an analytical methodology to predict forced convective CHF (Critical Heat Flux) for DNB (Departure from Nucleate Boiling) type boiling transition that occurs inside of uniformly heated round tubes. Axial directional two-phase flow analysis was conducted based on one-dimensional two-fluid model and typical constitutive models. At the same time, the radial directional distribution of void fraction at any axial location was calculated based on the bubble diffusion model, which was coupled with two-phase turbulence model for boiling bubbly flow. The calculated void fraction showed the wall peak distribution, and was compared with experimental data, which was derived from subcool boiling experiments. IPNVG (Incipient Point of Net Vapor Generation), which means the starting point of two-phase flow analysis, was also investigated well, since it was revealed that IPNVG had a significant influence on CHF prediction. By using this methodology for calculating radial directional void fraction distribution, we carried out CHF prediction for water on the assumption that DNB would occur when the local void fraction near the heated wall exceeds a critical value. The predicted CHF agreed well with experimental data, and the accuracy was within about 20%.
- 社団法人 日本原子力学会の論文
- 2003-10-25
著者
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KATAOKA Isao
Department of Mechanophysics Engineering, Osaka University
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Kataoka I
Department Of Mechanical Engineering Osaka University
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Kataoka I
Department Of Mechanophysics Engineering Osaka University
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Kodama Shigeo
Nuclear Fuel Industries Ltd
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Kataoka Isao
Department Of Mechanical Engineering Graduate School Of Engineering Osaka University
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Isao Kataoka
Department Of Mechanophysics Engineering Osaka University
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