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Pool boiling experiments in reduced graphene oxide colloids. Part Ⅰ - Boiling characteristics

机译:还原氧化石墨烯胶体的池沸腾实验。第一部分-沸腾特性

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摘要

Nucleate pool boiling characteristics were investigated in a reduced graphene oxide (RGO) colloid with a water base. Critical heat flux (CHF) pool boiling experiments were performed to analyze both the boiling heat transfer and the CHF on a silicon dioxide plate in colloids with concentrations of 0.0001,0.0005, and 0.0010 wt.%. The RGO colloid was prepared by chemical reduction of hydrazine from graphene oxide, and diluted for the experiments. In the boiling experiments, boiling heat transfer and CHF enhancement were shown to be related to the concentration. Special attention was focused on two phenomena: the enhanced CHF and improved boiling heat transfer in the RGO colloid. Possible mechanisms for these phenomena were examined from various viewpoints, including the RGO coating layer characteristics, wetta-bility, water absorption by the RGO porous medium, and history of the RGO coating layer development.
机译:在具有水基的还原氧化石墨烯(RGO)胶体中研究了核库沸腾特性。进行临界热通量(CHF)池沸腾实验,以分析浓度为0.0001、0.0005和0.0010 wt。%的胶体中的沸腾传热和二氧化硅板上的CHF。 RGO胶体是通过从氧化石墨烯化学还原肼制得的,并稀释后用于实验。在沸腾实验中,沸腾传热和CHF增强与浓度有关。特别关注的是两种现象:RGO胶体中CHF的增加和沸腾传热的改善。从各种角度研究了这些现象的可能机理,包括RGO涂层的特性,润湿性,RGO多孔介质的吸水率以及RGO涂层发展的历史。

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  • 来源
  • 作者单位

    Division of Mechanical System Engineering, Incheon National University, Incheon, Republic of Korea;

    Department of Mechanical Engineering, POSTECH, Pohang, Republic of Korea;

    Division of Advanced Nuclear Engineering, POSTECH, Pohang, Republic of Korea,Department of Mechanical Engineering, University of Michigan, Ann Arbor, USA;

    Division of Advanced Nuclear Engineering, POSTECH, Pohang, Republic of Korea;

  • 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

    Pool boiling; Critical heat flux; Boiling heat transfer; Graphene;

    机译:池沸腾;临界热通量;沸腾传热;石墨烯;

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