Time-resolved measurement of subchannel void distribution for boiling two-phase flow in 5x5 rod bundle at high-pressure and high-temperature

Takahiro Arai, Masahiro Furuya, Kenetsu Shirakawa, Yoshihisa Nishi

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)

Abstract

A subchannel void sensor (SCVS) was improved to acquire time-resolve boiling two-phase flow in a 5-by-5 heated rod bundle at high-pressure and high-temperature. The SCVS consists of 6-by-6 wire electrodes and 5-by-5 rod electrodes. The SCVS can acquire a time series data of local void fraction at 32 points of central subchannel region in addition to 100 points of rod surface regions between rods. The devised sensors are installed in the heated rod bundle at eight height levels to acquire two-phase flow dynamics and its development. The axial and radial power profile of the heated rod bundle are uniform, and eight pairs of sheath thermocouples are embedded on the heated rod to monitor its surface temperature distribution. The paper addresses the axial and cross-sectional distributions of void fraction at various pressure and rod bundle power conditions, which simulates an accidental condition in reactor core and in a spent fuel pool of a boiling water reactor (BWR). The experimental data are suitable to validate the computational multi-fluid dynamics (CMFD) and subchannel codes.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016
PublisherAmerican Nuclear Society
Pages193-200
Number of pages8
ISBN (Electronic)9780894487330
Publication statusPublished - 2016 Jan 1
Externally publishedYes
Event3rd International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 - New Orleans, United States
Duration: 2016 Jun 122016 Jun 16

Publication series

NameInternational Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016

Conference

Conference3rd International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016
CountryUnited States
CityNew Orleans
Period16/6/1216/6/16

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Keywords

  • Boiling two-phase flow
  • High pressure
  • Rod bundle
  • Subchannel void sensor
  • Void fraction

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Geotechnical Engineering and Engineering Geology
  • Nuclear and High Energy Physics

Cite this

Arai, T., Furuya, M., Shirakawa, K., & Nishi, Y. (2016). Time-resolved measurement of subchannel void distribution for boiling two-phase flow in 5x5 rod bundle at high-pressure and high-temperature. In International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 (pp. 193-200). (International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016). American Nuclear Society.