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Extraction and stripping tests of engineering-scale centrifugal contactors cascade system for spent nuclear fuel reprocessing

燃料再処理用の工学規模多段遠心抽出器システムの抽出及び逆抽出試験

竹内 正行; 荻野 英樹; 中林 弘樹; 荒井 陽一; 鷲谷 忠博; 加瀬 健; 中島 靖雄

Takeuchi, Masayuki; Ogino, Hideki; Nakabayashi, Hiroki; Arai, Yoichi; Washiya, Tadahiro; Kase, Takeshi; Nakajima, Yasuo

Japan Atomic Energy Agency has been developing centrifugal contactors for solvent extraction to apply to next generation reprocessing plant. We evaluated the extraction and stripping performances of engineering-scale centrifugal contactors cascade system by uranyl nitrate solution on 10 kg/h flowsheet. As results, the uranium concentration profiles from extraction and stripping tests were fairly consistent with ideal distribution equilibrium calculated by MIXSET-X code. The stage efficiencies for uranium extraction and stripping were quite high. It was estimated as nearly 100% for extraction and 97$$sim$$98% for stripping. The contactors cascade system gave rapid equilibrium of distribution, and uranium concentration profiles became stable in 10 minutes on both extraction and stripping sections. No overflow and entrainment were observed under regular operation during extraction and stripping tests. From mal-operation test with the motor stop of one stage on contactors cascade system, it can keep running without emergency shutdown by the preparation of at least two spare stages.

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パーセンタイル:49.61

分野:Nuclear Science & Technology

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