发明名称 SPENT NUCLEAR FUEL REPROCESSING METHOD
摘要 <p>PROBLEM TO BE SOLVED: To restrain noble metal from being mixed in recovered uranium and plutonium by using inert gas as cover gas on molten salt. SOLUTION: Inert gas not reacting on fuel components is used as cover gas on molten salt. The inert gas is preferably Ne, Ar, Kr, Xe, He or N2. For instance, a positive electrode 2 serving as a fuel basket is charged with spent nuclear fuel 1 and dipped in the molten salt 4 in a molten-salt electrolytic cell 3 while spraying argon serving as the inert gas thereon, and a cover 5 is closed. When a fixed current is carried with a uranium recovery negative electrode 6 as negative, and the positive electrode 2 serving as the basket, as positive, only uranium is precipitated on the negative electrode 6 to obtain uranium of high purity. Pu remains in the positive electrode 2 serving as the basket, and recovered. Noble metal is precipitated on an auxiliary negative electrode 7 together with a small quantity of uranium without being mixed in uranium and plutonium recovered by the negative electrode 6. Minor actinides are dissolved in the molten salt.</p>
申请公布号 JP2000298190(A) 申请公布日期 2000.10.24
申请号 JP19990106209 申请日期 1999.04.14
申请人 HITACHI LTD 发明人 SASAHIRA AKIRA;YOKOI HIROTO;KAWAMURA FUMIO
分类号 G21C19/44;G21F9/06;(IPC1-7):G21C19/44 主分类号 G21C19/44
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