Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle

Takahiro Arai*, Masahiro Furuya, Kenetsu Shirakawa

*この研究の対応する著者

研究成果: Article査読

1 被引用数 (Scopus)

抄録

A subchannel void sensor (SCVS) acquires the two-phase flow in a rod bundle as the time-series data of cross-sectional distributions. Herein, the temperature and pressure ranges of an SCVS were extended to include the rated conditions of boiling water reactors. The improved SCVSs were installed in a 5 × 5 heated rod bundle at eight height levels. In a boiling experiment using the rod bundle, the three-dimensional distributions of the boiling two-phase flow were measured over a wide pressure range (up to 7.2 MPa). The new experimental data were compared with existing experimental data and the results of a subchannel analysis. Experimental results were consistent with those of a high-energy X-ray computed tomography study of a heated rod bundle with the same geometry and under the same heat and flow conditions as those used in our study. The subchannel analysis code reproduced the experimental results fairly well, and the obtained database is applicable for validating and improving thermal-hydraulic analysis codes.

本文言語English
ページ(範囲)203-221
ページ数19
ジャーナルNuclear Technology
208
2
DOI
出版ステータスPublished - 2022
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 凝縮系物理学

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