首页> 外文期刊>Nuclear Technology >THERMAL-FLUID CHARACTERIZATIONS OF ZnO AND SiC NANOFLUIDS FOR ADVANCED NUCLEAR POWER PLANTS
【24h】

THERMAL-FLUID CHARACTERIZATIONS OF ZnO AND SiC NANOFLUIDS FOR ADVANCED NUCLEAR POWER PLANTS

机译:先进核电站中ZnO和SiC纳米流体的热流体表征

获取原文
获取原文并翻译 | 示例
       

摘要

Nanofluids including metal or metal-oxide nanopar-ticles have shown improved thermal performance compared to water. Introducing zinc into a water-containing component of the primary system of a boiling water reactor or pressurized water reactor nuclear power plant is known to prevent the deposition of radioactive cobalt and to reduce the possible susceptibility of component materials to corrosion. Also, it is well known that silicon carbide (SiC) is a promising material for advanced reactors. Therefore, preparations of zinc oxide (ZnO) and SiC nanofluids have been used in diverse methods tornreduce inconsistency of nanofluidperformance. Thermal-fluid characterizations were carried out under the control of the preparation methods. In addition, indirect checks by contact angle measurements of depositions have shown that ZnO and SiC nanofluids as a self-recovering/ healing coating solution can contribute to advanced nuclear safety systems in terms of the critical heat flux margin. The results show that more efforts are needed to develop the nanofluid formulation to tailor the desired properties.
机译:与水相比,包括金属或金属氧化物纳米粒子的纳米流体显示出改善的热性能。将锌引入沸水反应堆或压水反应堆核电站的主要系统的含水组分中是已知的,以防止放射性钴的沉积并降低组分材料对腐蚀的敏感性。同样,众所周知,碳化硅(SiC)是用于先进反应器的有前途的材料。因此,氧化锌(ZnO)和SiC纳米流体的制备已用于多种方法中,以减少纳米流体性能的不一致。在制备方法的控制下进行热流体表征。此外,通过沉积物的接触角测量进行的间接检查表明,ZnO和SiC纳米流体作为一种自回收/愈合涂层溶液,可以在临界热通量裕度方面为先进的核安全系统做出贡献。结果表明,需要更多的努力来开发纳米流体制剂以定制所需的性质。

著录项

  • 来源
    《Nuclear Technology》 |2010年第1期|16-27|共12页
  • 作者

    IN CHEOL BANG; JI HYUN KIM;

  • 作者单位

    Ulsan National Institute of Science and Technology, School of Energy Engineering #100, Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan Metropolitan City 689-805, Korea;

    Ulsan National Institute of Science and Technology, School of Energy Engineering #100, Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan Metropolitan City 689-805, Korea;

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

    advanced nuclear power plant; nanofluids; critical heat flux;

    机译:先进核电站;纳米流体临界热通量;
  • 入库时间 2022-08-18 00:43:51

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号