High-energy x-ray ct measurement of void fraction distribution around part length rods in a rod bundle at high pressure and temperatures

Takahiro Arai*, Atsushi Ui, Masahiro Furuya, Riichiro Okawa, Tsugumasa Iiyama, Shota Ueda, Kenetsu Shirakawa, Kazuaki Kito

*この研究の対応する著者

研究成果: Conference contribution

抄録

A boiling experiment was conducted to acquire a threedimensional void fraction distribution in a rod bundle with part length rods. The test section was a 5 × 5 heated rod bundle that partially simulated a BWR rod bundle, and three PLRs were arranged together in the corner. The heated length of the fulllength rod was 3.71 m, which is equal in length to an actual fuel rod in BWRs, whereas the heated length of the PLR was 1.85 m. The rod bundle exhibited an axially and radially uniform heat flux. Further, the local void fraction was quantified by normalizing the intensities in the CT images of the boiling twophase flow with those obtained under the liquid-phase and gasphase conditions. The cross-sectional void fraction distribution was acquired at six height levels. The experimental results exhibited the void distribution around PLRs with respect to a wide range of flow conditions, inlet temperatures, inlet flow rates, bundle thermal powers, and system pressures.

本文言語English
ホスト出版物のタイトルStudent Paper Competition; Thermal-Hydraulics; Verification and Validation
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
出版ステータスPublished - 2020
外部発表はい
イベント2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference - Virtual, Online
継続期間: 2020 4月 42020 4月 5

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
3

Conference

Conference2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
CityVirtual, Online
Period20/4/420/4/5

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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