Thermal-hydraulic experiments with sodium chloride aqueous solution
Jiao, L.; Liu, W.; 永武 拓; 高瀬 和之; 吉田 啓之; 永瀬 文久
Jiao, L.; Liu, W.; Nagatake, Taku; Takase, Kazuyuki; Yoshida, Hiroyuki; Nagase, Fumihisa
In Fukushima Daiichi nuclear disaster, seawater was injected into the nuclear core, which may change the heat transfer characteristics in the reactor pressure vessels (RPV) due to the different physical properties of seawater and pure water. To remove molten fuel from the Fukushima Daiichi Nuclear Power Plants, it is necessary to know the current status of the reactors. Therefore, in this paper, we measured the basic thermal-hydraulic data in an annular tube with a co-axial heater, which includes the heat transfer rate and the pressure drop, using the sodium chloride aqueous solutions and the synthetic seawater as working fluids. The experiments were performed under atmosphere pressure, with the salinity, the fluid mass flux, the inlet temperature and the heat flux used as the parameters. The experimental results and analyses are reported in this paper and the basic influence of the salinity on the heat transfer and the hydraulic characters are proposed.
使用言語 : English
掲載資料名 : Proceedings of 15th International Heat Transfer Conference (IHTC 2014) (USB Flash Drive)
ページ数 : 11 Pages
発行年月 : 2014/08
出版社名 :
発表会議名 : 15th International Heat Transfer Conference (IHTC 2014)
開催年月 : 2014/08
開催都市 : Kyoto
開催国 : Japan
特許データ :
論文URL :
キーワード : 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : BB20140301
抄録集掲載番号 : 42001163
論文投稿番号 : 14807
Accesses  (From Jun. 2, 2014)
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