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首页> 外文期刊>International Journal of Heat and Mass Transfer >Experimental investigation of transient critical heat flux of water-based zinc-oxide nanofluids
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Experimental investigation of transient critical heat flux of water-based zinc-oxide nanofluids

机译:水性氧化锌纳米流体瞬态临界热通量的实验研究

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摘要

Pool boiling experiments were conducted for sandblasted stainless steel (grade 316) plate heaters submerged in deionized (DI) water and water-based zinc-oxide nanofluid, for transient heat flux conditions with power through the heaters increasing quadratically with time. Heat flux in the experiments was increased from zero to CHF in short time frames of 1,10 and 100 s. Consistent with previous studies, transient CHF for DI water was higher than steady state CHF, and CHF increased with decreasing duration of the transient. Additionally, it was observed that for nanofluid tests, a porous and hydrophilic nanopaiticle layer started to deposit on the heater surface in short time frames of 10 and 100 s, and this layer was responsible for the enhanced CHF compared to DI water. However, for the 1 s tests, nanoparticle deposition did not occur and consequently the CHF was not enhanced. Finally, experiments with heaters pre-coated with nanoparticles were performed and it was found that CHF was enhanced for all transient durations down to 1 s, establishing firmly that the CHF enhancement occurs due to surface modifications by the deposited nanoparticles, and not by nanoparticles suspended in solution.
机译:对于浸没在去离子(DI)水和水基氧化锌纳米流体中的喷砂不锈钢(316级)平板加热器,进行了池沸腾实验,以求瞬态热通量条件,其中通过加热器的功率随时间呈二次方增加。实验中的热通量在1,10和100 s的短时间内从零增加到CHF。与先前的研究一致,去离子水的瞬态CHF高于稳态CHF,并且CHF随着瞬态持续时间的减少而增加。另外,观察到,对于纳米流体测试,在10到100 s的短时间内,多孔亲水性纳米颗粒层开始沉积在加热器表面,与DI水相比,该层负责提高CHF。但是,对于1 s测试,没有发生纳米颗粒沉积,因此CHF没有增强。最后,使用预涂有纳米颗粒的加热器进行了实验,发现在所有低至1 s的瞬态时间内,CHF均得到增强,从而牢固地确定了CHF增强是由于沉积的纳米颗粒而不是悬浮的纳米颗粒引起的表面改性在解决方案中。

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  • 作者单位

    Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Room 24-206, 77 Massachusetts Avenue, Cambridge, MA 02139-4307, USA;

    Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Room 24-206, 77 Massachusetts Avenue, Cambridge, MA 02139-4307, USA;

    Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Room 24-206, 77 Massachusetts Avenue, Cambridge, MA 02139-4307, USA;

    Nuclear Reactor Laboratory, 138 Albany Street, Massachusetts Institute of Technology. Cambridge, MA 02139, USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Transient CHF; Departure from nucleate boiling; Boiling crisis; Pool boiling;

    机译:瞬态CHF脱离核沸腾;沸腾的危机;泳池沸腾;

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