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

研究成果: Conference contribution

3 被引用数 (Scopus)

抄録

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.

本文言語English
ホスト出版物のタイトルInternational Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016
出版社American Nuclear Society
ページ193-200
ページ数8
ISBN(電子版)9780894487330
出版ステータスPublished - 2016
外部発表はい
イベント3rd International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 - New Orleans, United States
継続期間: 2016 6月 122016 6月 16

出版物シリーズ

名前International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016

Conference

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

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学
  • 地盤工学および土木地質学
  • 核物理学および高エネルギー物理学

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