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

Research output: Contribution to conferencePaper

3 Citations (Scopus)

Abstract

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.

Original languageEnglish
Publication statusPublished - 2015 Jan 1
Externally publishedYes
Event23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 - Chiba, Japan
Duration: 2015 May 172015 May 21

Conference

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

Fingerprint

Void fraction
Two phase flow
Boiling liquids
Accidents
Cooling
Reactor cores
Flow structure
Water levels
Thermocouples
Atmospheric pressure
Time series
Temperature distribution
Sensors
Experiments
Temperature

Keywords

  • 5×5 heated rod bundle
  • Boil-off
  • Boiling two-phase flow
  • Subchannel void sensor
  • Two-phase mixture level
  • Void fraction

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Arai, T., Furuya, M., Kanai, T., Shirakawa, K., & Nishi, Y. (2015). Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics. Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan.

Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics. / Arai, Takahiro; Furuya, Masahiro; Kanai, Taizo; Shirakawa, Kenetsu; Nishi, Yoshihisa.

2015. Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan.

Research output: Contribution to conferencePaper

Arai, T, Furuya, M, Kanai, T, Shirakawa, K & Nishi, Y 2015, 'Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics', Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan, 15/5/17 - 15/5/21.
Arai T, Furuya M, Kanai T, Shirakawa K, Nishi Y. Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics. 2015. Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan.
Arai, Takahiro ; Furuya, Masahiro ; Kanai, Taizo ; Shirakawa, Kenetsu ; Nishi, Yoshihisa. / Coolability height of 5×5 heated rod bundle in reference to collapsed level and boiling two-phase flow dynamics. Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan.
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