Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires

碩士 === 國立交通大學 === 機械工程系 === 88 === The performance of nucleate pool boiling of dielectric liquid FC-87 on horizontal wires were investigated in this study. In order to understand the pool boiling heat transfer characteristics for high wetting low surface tension dielectric liquid, the liquid were bo...

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Main Authors: Yi-Tai Tsai, 蔡伊泰
Other Authors: Ding-Chong Lu
Format: Others
Language:zh-TW
Published: 2000
Online Access:http://ndltd.ncl.edu.tw/handle/22596935506448710826
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spelling ndltd-TW-088NCTU04890592016-07-08T04:22:40Z http://ndltd.ncl.edu.tw/handle/22596935506448710826 Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires 介電液FC-87對水平加熱線池核沸騰熱傳分析 Yi-Tai Tsai 蔡伊泰 碩士 國立交通大學 機械工程系 88 The performance of nucleate pool boiling of dielectric liquid FC-87 on horizontal wires were investigated in this study. In order to understand the pool boiling heat transfer characteristics for high wetting low surface tension dielectric liquid, the liquid were boiled using 0.1-, 0.2- and 0.3-mm-diameter wires made of tungsten and molybdenum. The experimental results show that boiling heat transfer coefficients decreased withincreasing wire size. Compared tungsten and molybdenum of the same diameter, tungsten has higher heat transfer coefficients. The data showed incipience superheat of 17.8~32.2℃ and temperature excursion of 5~14℃. CHF occurs at heat flux between 1.7 105W/m2 and 2.35 105W/m2 ,and the smaller diameter wire has higher CHF .The Rohsenow correlation corrected by Danielson can predict experimental data of nucleate boiling heat transfer coefficients within 30% band of uncertainty. We can use You correlation to predict CHF , and prediction values are higher than experimental data. Ding-Chong Lu 盧定昶 2000 學位論文 ; thesis 59 zh-TW
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language zh-TW
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sources NDLTD
description 碩士 === 國立交通大學 === 機械工程系 === 88 === The performance of nucleate pool boiling of dielectric liquid FC-87 on horizontal wires were investigated in this study. In order to understand the pool boiling heat transfer characteristics for high wetting low surface tension dielectric liquid, the liquid were boiled using 0.1-, 0.2- and 0.3-mm-diameter wires made of tungsten and molybdenum. The experimental results show that boiling heat transfer coefficients decreased withincreasing wire size. Compared tungsten and molybdenum of the same diameter, tungsten has higher heat transfer coefficients. The data showed incipience superheat of 17.8~32.2℃ and temperature excursion of 5~14℃. CHF occurs at heat flux between 1.7 105W/m2 and 2.35 105W/m2 ,and the smaller diameter wire has higher CHF .The Rohsenow correlation corrected by Danielson can predict experimental data of nucleate boiling heat transfer coefficients within 30% band of uncertainty. We can use You correlation to predict CHF , and prediction values are higher than experimental data.
author2 Ding-Chong Lu
author_facet Ding-Chong Lu
Yi-Tai Tsai
蔡伊泰
author Yi-Tai Tsai
蔡伊泰
spellingShingle Yi-Tai Tsai
蔡伊泰
Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
author_sort Yi-Tai Tsai
title Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
title_short Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
title_full Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
title_fullStr Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
title_full_unstemmed Analysis of Nucleate Pool Boiling of FC-87 on Horizontal Wires
title_sort analysis of nucleate pool boiling of fc-87 on horizontal wires
publishDate 2000
url http://ndltd.ncl.edu.tw/handle/22596935506448710826
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