发明名称 PROCESSING METHOD FOR SPENT NUCLEAR FUEL
摘要 <p>PROBLEM TO BE SOLVED: To provide a processing method for spent nuclear fuel capable of reducing the accompanying quantity of metal unclear fuel components to the components of clad and the like to be waste, improving the recovery fraction of metal nuclear fuel component and reducing the quantity of waste of such component as clad. SOLUTION: Metal nuclear fuel material from which alloy clad is melted and separated by heating the processing object in the temperature over the melting point of alloy-made clad and below the melting point of the metal nuclear fuel material (in the melting separation process 2 of clad, etc.), alloy clad or end plugs is removed in the melting separation process 2 of clad is dipped in slat consisting of alkaline metal chloride, alkaline earth metal chloride or mixture of them in molten state to dissolve the metal nuclear fuel material. On the other hand, uranium, uranium and plutonium or uranium, plutonium and transuranium elements is precipitated (molten salt electrolyzing process 5). Then the processing object is taken out of the salt and the chloride or alkaline earth metals adhering to the precipitated elements is evaporated and separated by heating in normal or reduced pressure state (evaporation and separation process 6 and 9).</p>
申请公布号 JPH11118982(A) 申请公布日期 1999.04.30
申请号 JP19970285836 申请日期 1997.10.17
申请人 TOSHIBA CORP 发明人 KONDO NARUHITO;MATSUMARU KENICHI;FUJITA REIKO;FUJIE MAKOTO
分类号 G21C19/44;C25C3/34;G21C19/48;(IPC1-7):G21C19/44 主分类号 G21C19/44
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