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

Atsushi Ui*, Masahiro Furuya, Takahiro Arai, Kenetsu Shirakawa

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

1 Citation (Scopus)


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).

Original languageEnglish
Article number111323
JournalNuclear Engineering and Design
Publication statusPublished - 2021 Sept
Externally publishedYes


  • Bubble transport behavior
  • Interfacial area concentration
  • Temperature distribution
  • Void fraction

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • General Materials Science
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering


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