Interfacial area transport of subcooled boiling flow in a vertical annulus

Caleb S. Brooks, Basar Ozar, Takashi Hibiki, Mamoru Ishii

Research output: Contribution to journalArticlepeer-review


In an effort to improve the prediction of void fraction and heat transfer characteristics in two-phase systems, the two-group interfacial area transport equation has been developed for use with the two-group two-fluid model. The two-group approach treats spherical/distorted bubbles as Group-1 and cap/slug/churn-turbulent bubbles as Group-2. Therefore, the interfacial area transport of steam-water two-phase flow in a vertical annulus has been investigated experimentally, including bulk flow parameters and wall nucleation characteristics. The theoretical modeling of interfacial area transport equation with phase change terms is introduced and discussed along with the experimental results. Benchmark of the interfacial area transport equation is performed considering the effects of bubble interaction mechanisms such as bubble break-up and coalescence, as well as, effects of phase change mechanisms such as wall nucleation and condensation for subcooled boiling. From the benchmark, sensitivity in the constitutive relations for Group-1 phase change mechanisms, such as wall nucleation and condensation is clear. The Group-2 interfacial area transport is shown to be dominated by the interfacial heat transfer mechanism causing expansion of Group-1 bubbles into Group-2 bubbles in the boiling flow.

Original languageEnglish (US)
Pages (from-to)152-163
Number of pages12
JournalNuclear Engineering and Design
StatePublished - Mar 2014
Externally publishedYes

ASJC Scopus subject areas

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


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