Transient boiling flow in 5 × 5 rod bundle under non-uniform rapid heating

Hiroki Takiguchi*, Masahiro Furuya, Takahiro Arai, Kenetsu Shirakawa


研究成果: Article査読

4 被引用数 (Scopus)


Rapid thermal elevation in boiling water reactor (BWR) is an important factor for nuclear safety and there is a need to develop an analysis code for the transient phenomenon and its validation process. To evaluate the thermal property of transient boiling and its uncertainty, corroborative experimental information is crucial. In particular, the lateral propagation behavior of a vapor bubble (void) in the cross-sectional direction of fuel assembly has yet to be determined. This study evaluates the void propagation behavior in a 5 × 5 rod bundle with cross-sectional heat distribution that causes only the 3 × 3 rod bundle to generate heat; assuming rapid heating under atmospheric pressure. In this paper, using the maximum heat output applied to the nine heated rods as a parameter, from the visualization of the void behavior and the measurement of the local void fraction, the heat output conditions under circumstances where lateral propagation of voids occurs and where voids are only localized in the heated region are summarized. We quantified the time difference initially detected and the time-averaged void fraction according to the lateral propagation level.

ジャーナルNuclear Engineering and Design
出版ステータスPublished - 2018 12月 15

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
  • 材料科学(全般)
  • 安全性、リスク、信頼性、品質管理
  • 廃棄物管理と処理
  • 機械工学


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