Method of producing radioactive technetium-99M
    1.
    发明授权
    Method of producing radioactive technetium-99M 失效
    放射性锝-99M生产方法

    公开(公告)号:US4158700A

    公开(公告)日:1979-06-19

    申请号:US886404

    申请日:1978-03-14

    CPC classification number: C01G99/003 G21H5/02

    Abstract: A chromatographic process of producing high purity and high yield radioactive Technetium-99m. A solution containing Molybdenum-99 and Technetium-99m is placed on a chromatographic column and eluted with a neutral solvent system comprising an organic solvent and from about 0.1 to less than about 10% of water or from about 1 to less than about 70% of a solvent selected from the group consisting of aliphatic alcohols having 1-6 carbon atoms. The eluted solvent system containing the Technetium-99m is then removed leaving the Technetium-99m as a dry, particulate residue.

    Abstract translation: 生产高纯度高产放射性锝-99m的色谱法。 将含有钼-99和锝-99m的溶液置于色谱柱上,并用包含有机溶剂和约0.1至小于约10%的水或约1至小于约70%的中性溶剂系统洗脱 选自具有1-6个碳原子的脂族醇的溶剂。 然后除去含有锝-99m的洗脱溶剂系统,留下锝-99m作为干燥的颗粒残余物。

    TECHNETIUM RECOVERY FROM HIGH ALKALINE SOLUTION
    3.
    发明申请
    TECHNETIUM RECOVERY FROM HIGH ALKALINE SOLUTION 有权
    高碱解决方案的技术回收

    公开(公告)号:US20160177421A1

    公开(公告)日:2016-06-23

    申请号:US14576362

    申请日:2014-12-19

    Inventor: Charles A. Nash

    Abstract: Disclosed are methods for recovering technetium from a highly alkaline solution. The highly alkaline solution can be a liquid waste solution from a nuclear waste processing system. Methods can include combining the solution with a reductant capable of reducing technetium at the high pH of the solution and adding to or forming in the solution an adsorbent capable of adsorbing the precipitated technetium at the high pH of the solution.

    Abstract translation: 公开了从高碱性溶液中回收锝的方法。 高碱性溶液可以是来自核废料处理系统的废液。 方法可以包括将溶液与能够在溶液的高pH下还原锝的还原剂组合,并在该溶液中加入或形成能够在溶液的高pH下吸附沉淀的锝的吸附剂。

    Separation of uranium from technetium in recovery of spent nuclear fuel
    5.
    发明授权
    Separation of uranium from technetium in recovery of spent nuclear fuel 失效
    在废核燃料回收中将铀与锝分离

    公开(公告)号:US4528165A

    公开(公告)日:1985-07-09

    申请号:US559501

    申请日:1984-06-13

    Abstract: A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.

    Abstract translation: 从Purex工艺中净化铀产品的方法包括向含有六价(UO22 +)铀和七价锝(TcO4-)的Purex工艺的硝酸铀酰产物中加入肼。 产物流中的锝减少,然后通过加入草酸(H 2 C 2 O 4)络合,并且Tc-草酸盐络合物通过溶剂萃取容易地与铀分离,30体积%。 磷酸三丁酯在正十二烷中。

    Method and device for producing 99mTc
    7.
    发明授权
    Method and device for producing 99mTc 有权
    生产99mTc的方法和装置

    公开(公告)号:US09576692B2

    公开(公告)日:2017-02-21

    申请号:US13576475

    申请日:2011-01-20

    Abstract: A method for producing 99mTc may include: providing a solution comprising 100Mo-molybdate-ions; providing a proton beam having an energy suitable for inducing a 100Mo(p,2n)99mTc-nuclear reaction when exposing 100Mo-molybdate-ions; exposing the solution to the proton beams and inducing a 100Mo(p,2n)99mTc-nuclear reaction; and applying an extraction method for extracting the 99mTc from the solution. Further, a device for producing 99mTc may include: a solution with 100Mo-molybdate-ions; an accelerator for providing a proton beam with energy which is suitable for inducing a 100Mo(p,2n)99mTc-nuclear reaction when exposing 100Mo-molybdate-ions, for exposing the solution and for inducing a 100Mo(p,2n)99mTc-nuclear reaction; and an extraction step for extracting 99mTc from the solution.

    Abstract translation: 制备99mTc的方法可以包括:提供包含100M钼酸盐离子的溶液; 提供具有适于在暴露100M钼酸盐离子时诱导100Mo(p,2n)99mTc-核反应的能量的质子束; 将溶液暴露于质子束并诱导100Mo(p,2n)99m Tc核反应; 并从溶液中提取提取99mTc的提取方法。 此外,用于制备99mTc的装置可以包括:具有100M钼酸根离子的溶液; 用于提供质子束具有能量的加速器,其适于在暴露100M钼酸盐离子时诱导100Mo(p,2n)99mTc-核反应,用于暴露溶液和诱导100Mo(p,2n)99mTc-核 反应; 以及从溶液中提取99mTc的提取步骤。

    Robust technetium removal method and system
    8.
    发明授权
    Robust technetium removal method and system 失效
    强大的锝去除方法和系统

    公开(公告)号:US5954936A

    公开(公告)日:1999-09-21

    申请号:US818484

    申请日:1997-03-14

    CPC classification number: C01G99/003 B01J47/04 B01J47/08

    Abstract: The invention provides a method and processing system for removing both anionic and cationic technetium complexes from an aqueous solution by adjusting the pH of the solution to greater than approximately 2, and directing the solution into an integrated resin and electrochemical plating device. The integrated resin and plating device has a resin bed or resin membrane in which is disposed one or more cathodes, and one or more anodes. A potential generator produces at least a 1 volt potential between the cathodes and the anodes. As the solution passes through the resin, the technetium complexes are adsorbed onto it. When a sufficient concentration of technetium complexes is adsorbed, the plating process can atlernatively be driven to plate out the technetium onto the cathodes, or to collect various species in system anolytes/catholytes.

    Abstract translation: 本发明提供了一种方法和处理系统,用于通过将溶液的pH调节至大约2,从而将水溶液中的阴离子和阳离子锝络合物除去,并将溶液引导到一体化树脂和电化学电镀装置中。 集成树脂和电镀装置具有树脂床或树脂膜,其中设置有一个或多个阴极和一个或多个阳极。 电位发生器在阴极和阳极之间产生至少1伏的电位。 当溶液通过树脂时,锝络合物被吸附在其上。 当吸附足够浓度的锝络合物时,电镀过程可以被驱赶,将锝沉积到阴极上,或者在系统的阳极液/阴极液中收集各种物质。

    Process for the separation of actinides from lanthanides by the
selective extraction of the actinides in an organic solvent
incorporating a propane diamide
    9.
    发明授权
    Process for the separation of actinides from lanthanides by the selective extraction of the actinides in an organic solvent incorporating a propane diamide 失效
    通过选择性提取掺入丙二酰胺的有机溶剂中锕系元素将锕系元素从镧系元素分离的方法

    公开(公告)号:US5256383A

    公开(公告)日:1993-10-26

    申请号:US929677

    申请日:1992-08-13

    Abstract: The invention relates to a process for the separation of actinides from lanthanides by the selective extraction of the actinides in an organic solvent incorporating a propane diamide.This process consists of adding to the aqueous nitric solution containing the actinides and lanthanides a thiocyanate, e.g. ammonium thiocyanate, followed by the contacting of said solution with an organic solvent incorporating at least one propane diamide, e.g. 2-tetradecyl-N,N'-dimethyl-N,N'-dibutyl-propane diamide and optionally a quaternary ammonium salt such as trilauryl methyl ammonium (TMA) thiocyanate or a mixture of quaternary ammonium thiocyanates.This leads to distribution coefficients D.sub.M for the actinides (Am) and the lanthanides (Eu, Ce) making it possible to achieve high actinide/lanthanide separation factors.

    Abstract translation: 本发明涉及通过在掺入丙二酰胺的有机溶剂中选择性萃取锕系元素从镧系元素分离锕系元素的方法。 该方法包括加入含有锕系元素和硫氰酸盐的镧系元素的含水硝酸溶液。 硫氰酸铵,然后使所述溶液与引入至少一种丙二醇的有机溶剂接触。 2-十四烷基-N,N'-二甲基-N,N'-二丁基丙烷二酰胺和任选的季铵盐如三月桂基甲基铵(TMA)硫氰酸酯或季铵硫氰酸酯的混合物。 这导致锕系元素(Am)和镧系元素(Eu,Ce)的分布系数DM使得可以实现高锕系元素/镧系元素分离因子。

    Treatment of technetium containing solutions
    10.
    发明授权
    Treatment of technetium containing solutions 失效
    含锝溶液的处理

    公开(公告)号:US4738834A

    公开(公告)日:1988-04-19

    申请号:US701373

    申请日:1985-02-14

    Abstract: An initial aqueous pertechnetate solution which has a low electrolyte concentration compared with physiological saline is treated by passage through a bed of insoluble ion exchange material for adsorbing the pertechnetate. In a second step an ionic eluant having a smaller volume than the pertechnetate solution is passed through the bed to remove the pertechnetate to provide a relatively concentrated and pure eluate solution, the ion exchange material in the bed and the ionic eluant having respective properties for providing the eluate with a pH suitable for radiopharmaceutical purposes. The bed retains thereon radionuclidic impurities which may have been in the initial solution. The method can be valuable for treating the eluate from a portable technetium generator which is eluted with water and advantageously the insoluble material in the bed is zirconium oxide.

    Abstract translation: 与生理盐水相比具有低电解质浓度的初始高锝酸盐水溶液通过不溶离离子交换材料床进行处理,以吸附高锝酸盐。 在第二步中,具有比高锝酸盐溶液体积小的离子洗脱剂通过床以除去高锝酸盐以提供相对浓缩和纯的洗脱液,床中的离子交换材料和离子洗脱剂具有各自的性质,用于提供 具有适合放射性药物目的的pH值的洗脱液。 床上保留有可能在初始溶液中的放射性核素杂质。 该方法对于从用水洗脱的便携式锝发生器处理洗脱液可能是有价值的,并且有利的是床中的不溶物质是氧化锆。

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