Measurement of forced convection subcooled boiling flow and rod surface temperature distribution

Atsushi Ui, Masahiro Furuya, Takahiro Arai, Kenetsu Shirakawa

研究成果: Article査読

抄録

In order to obtain high-resolution data for modelling of boiling two-phase flow and its validation, we designed and constructed a test loop with a vertical annulus flow path and conducted subcooled boiling experiments to investigate subcooled bubble incipience and its development process under atmospheric condition. Three kinds of the state-of-the art measurement techniques were applied to quantify key parameters such as radial and vertical distributions of void fraction, bubble velocity, interfacial area concentration (IAC), Sauter mean diameters, high-resolution temperature distribution on rod surface, bubble transport behavior, and turbulent velocity components as well as onset of nucleate boiling (ONB), and onset of significant void (OSV).

本文言語English
論文番号111323
ジャーナルNuclear Engineering and Design
381
DOI
出版ステータスPublished - 2021 9
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 安全性、リスク、信頼性、品質管理
  • 廃棄物管理と処理
  • 機械工学

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