Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics

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

研究成果査読

3 被引用数 (Scopus)

抄録

In accidents when the water level of the reactor core descends below the top of the active fuel, the cooling limit height is a key factor in determining the accident mitigation procedure and the boiling two-phase flow in a fuel-rod bundle exhibits multi-dimensional and complex flow structures during such boil-off process. A rod bundle boil-off experiment was conducted to determine the three-dimensional void-fraction distribution and axial profile of the rod-surface temperature during the boil-off process under atmospheric pressure conditions. The 5×5 rod bundle, featuring a heated length of 2 m, had an axially and radially uniform power profile, with eight pairs of sheath thermocouples embedded on the heated rod to monitor its surface temperature distribution. The void-fraction distribution was acquired with five pairs of SubChannel Void Sensor (SCVS) as time-series data. The experimental results showed the relationship between an effective cooling level and boiling two-phase flow dynamics in the rod bundle.

本文言語English
出版ステータスPublished - 2015 1 1
外部発表はい
イベント23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 - Chiba, Japan
継続期間: 2015 5 172015 5 21

Conference

Conference23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
国/地域Japan
CityChiba
Period15/5/1715/5/21

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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