发明名称 RECOVERY METHOD FOR URANIUM OXIDE
摘要 <p>PROBLEM TO BE SOLVED: To provide a uranium-recovery method without new generation of radioactive waste liquid or waste solvent which can simplify reprocess and precipitate uranium oxide on cathode surface at low temperature, and extremely reduce the corrosion of recovery device. SOLUTION: Nitrate containing uranium nitrate is heated to arrange molten salt 13, the molten salt is electrolyzed by arranging a pair of electrodes to be an anode 17 and a cathode 18 in the molten salt, and uranium oxide 24 is precipitated on the surface of the cathode 18. For the nitrate containing uranium nitrate, mixture of uranium nitrate and one or two kinds of nitrate selected from sodium nitrate, potassium nitrate, calcium nitrate and magnesium nitrate can be raised.</p>
申请公布号 JPH0933688(A) 申请公布日期 1997.02.07
申请号 JP19950181177 申请日期 1995.07.18
申请人 MITSUBISHI MATERIALS CORP 发明人 OTA KAZUAKI;TAKAZAWA HIROSHI;TERAMAE NAOKI;ONOE TAKESHI
分类号 G21C19/44;C01G43/01;(IPC1-7):G21C19/44 主分类号 G21C19/44
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