Film-droplet split correlation at the onset of annular-mist flow

S. Oh, B. Hizoum, P. Saha, B. Dooies, D. Miranda, J. G.M. Andersen

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

7 Scopus citations

Abstract

Boiling transition in BWR fuels occurs in the annular-mist flow regime. Many subchannel analysis methods have been developed to predict critical power, as well as flow and void distributions, in BWR fuel bundles. Two-phase annular-mist flow can be better simulated with two-fluid, three-field formulations for liquid film flow on surfaces, vapor and entrained droplet flows inside the core of the subchannel. To predict dryout of BWR fuels in the annular flow regime, the liquid film mass balance is analyzed using appropriate droplet entrainment and deposition models along with evaporation to determine the condition when film dries out or a dry patch forms (i.e. boiling transition). It is of great importance to define a correct boundary condition for the liquid flow split between the liquid film and entrained droplets at the onset of annular flow to accurately model the entrainment and deposition at the downstream annular flow, predict dryout location and corresponding critical power. No reliable information on the film-droplet split at onset of annular flow have been found in the literature and most analyses have been performed with an assumption that a single value is valid for wide ranges of operating conditions. In this study, a new film-droplet split correlation in the form of film fraction is developed based on available data with steam-water experiments. The liquid split correlation is then applied to simulate film flow measurement data over a wide range of exit quality.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages8695-8706
Number of pages12
ISBN (Electronic)9781510811843
StatePublished - 2015
Externally publishedYes
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume10

Conference

Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period08/30/1509/4/15

Keywords

  • Annular flow
  • Boiling transition
  • Entrainment
  • Film-droplet split
  • Subchannel analysis

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