发明名称 DECONTAMINATING METHOD FOR TECHNETIUM IN CO-DECONTAMINATION STEP IN REPROCESSING PROCESS OF SPENT NUCLEAR FUEL
摘要 <p>PURPOSE:To simplify a processing step and reduce costs by uniting a Tc stripping solution from a Tc stripping step set after a main extracting/cleaning step in a co-decontamination step of a reprocessing process, at a cleaning step of the precedent process. CONSTITUTION:In a co-decontamination step of a reprocessing purex process of spent fuel, septivalent technetium Tc (VII) extracted in a U-Pu organic product through the co-extraction of Zr, Pu and U is removed from the organic phase and discharged in a high-level water-phase waste liquid. For this purpose, a Tc stripping step is arranged after a main extracting/cleaning step in the co-decontamination process. The aqueous solution containing the stripped Tc is injected between a feeding stage of a feed liquid and a feeding stage of an extraction solvent in the main extracting/cleaning step, so that the Tc is discharged into the high-level water-phase waste liquid quantitatively.</p>
申请公布号 JPH0712986(A) 申请公布日期 1995.01.17
申请号 JP19930149335 申请日期 1993.06.21
申请人 JAPAN ATOM ENERGY RES INST 发明人 TATEMORI KATSUICHI
分类号 G21C19/46;G21F9/06;(IPC1-7):G21C19/46 主分类号 G21C19/46
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