Transient boiling and cross flow in 5×5 ROD bundle with rapid heating

Hiroki Takiguchi, Masahiro Furuya, Takahiro Arai, Kenetsu Shirakawa

研究成果: Conference contribution

抄録

Rapid thermal elevation in nuclear reactor is an important factor for nuclear safety. It is indispensable to develop a three-dimensional nuclear thermal transient analysis code and confirm its validity in order to accurately evaluate the effectiveness of the running nuclear safety measures when heating power of reactor core rapidly rises. However, the heat transfer characteristics such as reactivity feedback characteristics due to moderator density and the technical knowledge explaining the uncertainty are insufficient. In particular, the cross propagation behavior of vapor bubble (void) in cross section of fuel assembly is not grasped. This study evaluates the cross propagation void behavior in a simulated fuel assembly at time of rapid heat generation with a thermal hydraulic test loop including a 5×5 rod bundle having the heat generation profile in the flow cross sectional direction. In this paper, the branching heat output condition of transient cross propagation was investigated from visualization of high speed video camera and void fraction measurement by wire mesh sensor with the inlet flow rate 0.3m/s and the inlet coolant temperature 40oC, which are based on the transient safety analysis condition. In addition, we applied the particle imaging velocimetry (PIV) technique to measure liquid-phase velocity profile of the coolant in the transient cross flow and experimentally clarified the relationship with the cross flow.

本文言語English
ホスト出版物のタイトルThermal-Hydraulics and Safety Analyses
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
DOI
出版ステータスPublished - 2018 1 1
外部発表はい
イベント2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
継続期間: 2018 7 222018 7 26

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
6A

Other

Other2018 26th International Conference on Nuclear Engineering, ICONE 2018
CountryUnited Kingdom
CityLondon
Period18/7/2218/7/26

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

フィンガープリント 「Transient boiling and cross flow in 5×5 ROD bundle with rapid heating」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル