ICONE23-1551 COOLABILITY HEIGHT OF 5×5 HEATED ROD BUNDLE IN REFERENCE TO COLLAPSED LEVEL AND BOILING TWO-PHASE FLOW DYNAMICS
-
- Arai Takahiro
- Central Research Institute of Electric Power Industry
-
- Furuya Masahiro
- Central Research Institute of Electric Power Industry
-
- Kanai Taizo
- Central Research Institute of Electric Power Industry
-
- Shirakawa Kenetsu
- Central Research Institute of Electric Power Industry
-
- Nishi Yoshihisa
- Central Research Institute of Electric Power Industry
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.
収録刊行物
-
- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
-
Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2015.23 (0), _ICONE23-1-_ICONE23-1, 2015
一般社団法人 日本機械学会
- Tweet
キーワード
詳細情報
-
- CRID
- 1390282680857581312
-
- NII論文ID
- 110010046337
-
- ISSN
- 24242934
-
- 本文言語コード
- en
-
- データソース種別
-
- JaLC
- Crossref
- CiNii Articles
-
- 抄録ライセンスフラグ
- 使用不可