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4 条记录 (耗时 0.011 秒)

    Process for the recovery of plutonium contained in solid waste
    1.
    发明授权
    Process for the recovery of plutonium contained in solid waste 失效
    回收固体废物中所含钚的方法

    公开(公告)号：US4749519A

    公开(公告)日：1988-06-07

    申请号：US47635

    申请日：1987-05-07

    申请人： Gerard Koehly ,  Jacques Bourges ,  Charles Madic ,  Michael Lecomte

    发明人： Gerard Koehly ,  Jacques Bourges ,  Charles Madic ,  Michael Lecomte

    IPC分类号： C01G56/00 ,  C22B3/04 ,  C22B60/04 ,  G21C19/46 ,  G21F9/00 ,  G21F9/30 ,  C25C1/22 ,  G21C ,  G21C19/44

    CPC分类号： C22B3/045 ,  C22B60/04 ,  G21F9/30 ,  Y02P10/234

    摘要： The invention relates to a process for recovering the plutonium contained in the solid waste, such as process, technological and laboratory waste.The waste is contacted with aqueous nitric acid solution having a nitric acid concentration of 2 to 8 mole/l, which contains a compound of Ag.sup.2+ soluble in the solution, for oxidizing the plutonium present in the waste and for dissolving same in the nitric solution.Preferably, contacting takes place in an electrolytic cell having an anode and a cathode, by applying a potential difference between anode and cathode which is sufficient to continuously regenerate the Ag.sup.2+ ions used for oxidizing the elements present in said waste.

    摘要翻译： 本发明涉及一种用于回收固体废物中所含钚的方法，例如过程，技术和实验室废物。 将废物与硝酸浓度为2〜8摩尔/升的硝酸水溶液接触，其含有可溶于溶液中的Ag 2+化合物，用于氧化存在于废物中的钚并将其溶解在硝酸溶液中。 优选地，在具有阳极和阴极的电解池中进行接触，通过施加阳极和阴极之间的电位差，其足以连续地再生用于氧化存在于所述废物中的元素的Ag 2+离子。

    Process for the recovery of molybdenum-99 from an irradiated uranium alloy target
    2.
    发明授权
    Process for the recovery of molybdenum-99 from an irradiated uranium alloy target 失效
    从辐射铀合金靶材回收钼-99的工艺

    公开(公告)号：US4701308A

    公开(公告)日：1987-10-20

    申请号：US806815

    申请日：1985-12-10

    申请人： Gerard Koehly ,  Charles Madic

    发明人： Gerard Koehly ,  Charles Madic

    IPC分类号： C22B34/34 ,  C01G39/00 ,  C22B3/32 ,  G21C19/46 ,  G21G1/08

    CPC分类号： C22B3/0024 ,  C01G39/003 ,  G21C19/46 ,  G21G1/08 ,  Y02P10/234 ,  Y02W30/883

    摘要： The invention relates to a process for the recovery of molybdenum-99 from an irradiated uranium alloy target.This process comprises the following stages:(a) dissolving the irradiated uranium alloy target in sulphuric acid,(b) separating the iodine and tellurium present in the thus obtained solution,(c) oxidizing the molybdenum-99 present in the Mo (VI) solution, and(d) extracting the thus oxidized molybdenum-99 with a hydroxamic acid of formula: ##STR1## in which R is a radical chosen from the group including straight or branched-chain alkyl radicals, the phenyl radical, phenyl radicals substituted by at least one alkyl radical, arylalkyl radicals and the cyclohexyl radical and R' is a hydrogen atom or an alkyl radical.The hydroxamic acid can be tri-n-butylacetohydroxamic acid and the molybdenum recovered can be used in a technetium generator for medical purposes.

    摘要翻译： 本发明涉及从被照射的铀合金靶中回收钼-99的方法。 该方法包括以下步骤：（a）将照射的铀合金靶材溶解在硫酸中，（b）分离由此得到的溶液中存在的碘和碲，（c）氧化Mo（Ⅵ）中存在的钼-99， 溶液，和（d）用下式的异羟肟酸提取如此氧化的钼-99：其中R是选自直链或支链烷基的基团，苯基，苯基 由至少一个烷基，芳基烷基和环己基取代的基团，R'是氢原子或烷基。 异羟肟酸可以是三正丁基乙酰肟酸，所回收的钼可用于医疗用锝发生器。