Development of a multi-dimensional measurement sensor of void fraction and phasic velocity for boiling two-phase flow in a 5×5 heated rod bundle

Takahiro Arai*, Masahiro Furuya, Taizo Kanai, Kenetsu Shirakawa, Yoshihisa Nishi

*この研究の対応する著者

研究成果: Conference contribution

4 被引用数 (Scopus)

抄録

A subchannel void sensor (SCVS) was developed to measure the cross-sectional distribution of a void fraction in a 5×5 heated rod bundle with o.d. 10 mm and heated length 2000 mm, and applied in a boiling two-phase flow experiment under the atmospheric conditions assumed in an accident and spent fuel pool. The SCVS comprises 6-wire by 6-wire and 5-rod by 5-rod electrodes. Wire electrodes 0.2 mm in diameter are arranged in latticed patterns between the rod bundle, while a conductance value in a region near one wire and another gives a local void fraction in the central-subchannel region. 32 points (= 6×6-4) of the local void fraction can be obtained as a crosssectional distribution. In addition, a local void fraction near the rod surface can be estimated by a conductance value in a region near one wire and one rod using the simulated fuel rods as rod electrodes, which allows 100 additional points (=4×25) of the local void fraction to be acquired. The devised sensors are installed at five height levels to acquire two-phase flow dynamics in an axial direction. A pair of SCVS is mounted at each level and placed 30 mm apart to estimate the onedimensional phasic velocity distribution based on the crosscorrelation analysis of both layers. The time resolution of void measurement exceeds 800 frames (cross-sections) per second. The heated rod bundle has an axially and radially uniform power profile, and eight pairs of sheath thermocouples are embedded on the heated rod to monitor its surface temperature distribution. The boiling two-phase flow experiment, which simulated a boil-off process, was conducted with the devised SCVS and experimental data was acquired under various experimental conditions, such as inlet-flow velocity, rod-bundle power and inlet subcooling. The experimental results exhibited axial and radial distribution of two-phase flow structures, i.e. void-fraction and phasic-velocity distributions quantitatively.

本文言語English
ホスト出版物のタイトルThermal Hydraulics
出版社American Society of Mechanical Engineers (ASME)
ISBN(電子版)9780791845905
DOI
出版ステータスPublished - 2014 1月 1
外部発表はい
イベント2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic
継続期間: 2014 7月 72014 7月 11

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
2A

Conference

Conference2014 22nd International Conference on Nuclear Engineering, ICONE 2014
国/地域Czech Republic
CityPrague
Period14/7/714/7/11

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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