发明名称 VERFAHREN ZUM TRENNEN VON TECHNETIUM, DAS SICH IN EINER ORGANISCHEN LOESUNG MIT ZIRKON UND MINDESTENS EINEM ANDEREN METALL, WIE ZUM BEISPIEL URAN ODER PLUTONIUM, BEFINDET, VERWENDBAR INSBESONDERE FUER DIE WIEDERAUFARBEITUNG VON BESTRAHLTEN KERNBRENNSTOFFEN.
摘要 <p>Process for separating off the technetium present in an organic solvent in the first stage of treatment of irradiated nuclear fuels. In the reprocessing plant the solvent leaving the extractor 1 contains uranium, plutonium, zirconium and technetium; the zirconium is separated therefrom in the extractor (2) and then the technetium in the extractor (3) by being brought into contact with a solution of nitric acid and/or of nitrates which is preferably introduced at different concentrations at (19) and at (21). The solvent leaving the extractor (3) then contains only traces of technetium. The aqueous solution leaving the extractor (3) is treated in an extractor (4) with an organic solvent in order to re-extract into it the uranium and plutonium which have been transferred into aqueous solution. The technetium can thus be removed successfully before the uranium/plutonium partition operation is carried out, without introducing new chemical reactants and without greatly increasing the volume of the effluents leaving the plant. <IMAGE></p>
申请公布号 DE3784647(D1) 申请公布日期 1993.04.15
申请号 DE19873784647 申请日期 1987.11.26
申请人 COMMISSARIAT A L'ENERGIE ATOMIQUE, PARIS, FR;SOCIETE GENERALE POUR LES TECHNIQUES NOUVELLES S.G.N., SAINT-QUENTIN-EN-YVELINES, FR 发明人 BOULLIS BERNARD, BOULLIS BERNARD, F-92290 CHATENAY MALABRY, FR;GUE, JEAN-PAUL, F-92260 FONTENAY AUX ROSES, FR;BERNARD, CLAUDE, F-78410 SAINT REMY LES CHEVREUSES, FR
分类号 C01G56/00;C01G99/00;C22B34/14;C22B60/02;C22B60/04;C22B61/00;G21C19/46;(IPC1-7):G21C19/46;C01G57/00 主分类号 C01G56/00
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