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    Extraction of radionuclides by crown ether-containing extractants
    22.
    发明授权
    Extraction of radionuclides by crown ether-containing extractants 有权
    用含冠醚萃取剂提取放射性核素

    公开(公告)号：US07927566B2

    公开(公告)日：2011-04-19

    申请号：US11574825

    申请日：2004-09-09

    申请人： Jury Vasilievich Glagolenko ,  Mikhail Vasilievich Logunov ,  Igor Vitalievich Mamakin ,  Vladimir Mikhailovich Polosin ,  Sergey Ivanovich Rovny ,  Vadim Alexandrovich Starchenko ,  Jury Pavlovich Shishelov ,  Nikolay Gennadievich Yakovlev

    发明人： Jury Vasilievich Glagolenko ,  Mikhail Vasilievich Logunov ,  Igor Vitalievich Mamakin ,  Vladimir Mikhailovich Polosin ,  Sergey Ivanovich Rovny ,  Vadim Alexandrovich Starchenko ,  Jury Pavlovich Shishelov ,  Nikolay Gennadievich Yakovlev

    IPC分类号： C01F13/00

    CPC分类号： G21F9/12 ,  G21C19/46 ,  G21F9/04 ,  Y02W30/883

    摘要： The present invention relates to a treatment of high-level waste of radiochemical production containing radionuclides and macro-admixtures including sodium. The method of extraction of radionuclides by processing acidic aqueous waste solutions by extractants containing macrocyclic compounds selected from the group of crown ethers having aromatic fragments containing alkyl and/or hydroxyalkyl substituents of a linear and/or branched structure, and/or cyclohexane fragments containing alkyl and/or hydroxyalkyl substituents of a linear and/or branched structure, and/or fragments of —O—CHR—CH2O—, where R is the normal or branched alkyl or hydroxyalkyl in organic solvents containing polyfluorinated telomeric alcohol 1,1,7-trihydrododecafluoroheptanol-1 having the formula H(CF2CF2)nCH2OH, where n=3, and a mixture of polyoxyethylene glycol ethers of synthetic primary higher aliphatic alcohols of a fraction C12-C14 of a general formula CnH2n+1O(C2H4O)mH, where n=12-14, m=2 is proposed. A possibility of selection of quantitative and qualitative composition of the extractant depending on the waste composition and the object to be achieved of joint or individual extraction of radionuclides results in universal technology. A method of regeneration of extractants containing crown ethers allowing one to carry out the operation of extraction of radionuclides in a commercial scale under countercurrent dynamic conditions, with regeneration of the extractant for reuse is also proposed.

    摘要翻译： 本发明涉及含有放射性核素和包括钠在内的大分子混合物的放射化学生产高级废物的处理。 通过含有大环化合物的萃取剂处理酸性废水溶液来提取放射性核素的方法，所述萃取剂选自具有含有直链和/或支链结构的烷基和/或羟基烷基取代基的芳族片段的冠醚，和/或含烷基的环己烷片段 和/或直链和/或支链结构的羟基烷基取代基和/或-O-CHR-CH 2 O-的片段，其中R是含有多氟化端粒醇的有机溶剂中的正链或支链烷基或羟烷基， 具有式H（CF 2 CF 2）n CH 2 OH，n = 3的三氢十二氟庚醇-1和通式C n H 2n + 1 O（C 2 H 4 O）m H的级分C 12 -C 14的合成的初级高级脂族醇的聚氧乙二醇醚的混合物，其中n = 12-14，建议m = 2。 取决于废物组成以及要实现的放射性核素的联合或单独提取的目的，萃取剂的定量和定性组成的可能性导致通用技术。 还提出了一种再生含有冠醚的萃取剂的方法，其允许在逆流动态条件下以商业规模进行放射性核素的操作，再提取物再利用。

    Method and system for recovering metal from metal-containing materials
    25.
    发明授权
    Method and system for recovering metal from metal-containing materials 有权
    从含金属材料中回收金属的方法和系统

    公开(公告)号：US07686865B2

    公开(公告)日：2010-03-30

    申请号：US11795424

    申请日：2006-01-12

    申请人： Chien M. Wai ,  Sydney S. Koegler

    发明人： Chien M. Wai ,  Sydney S. Koegler

    IPC分类号： C22B60/02 ,  C22B60/04 ,  C22B3/26

    CPC分类号： C01G43/003 ,  B01D11/0203 ,  B01D11/0284 ,  B01D11/0288 ,  B01D11/0292 ,  C01P2006/80 ,  C22B3/0005 ,  C22B3/02 ,  C22B60/0239 ,  C22B60/026 ,  C22B60/04 ,  G21C19/46 ,  Y02P10/234 ,  Y02P20/544 ,  Y02W30/883

    摘要： Embodiments of a method and a system for recovering a metal, such as uranium, from a metal-containing material are disclosed. The metal-containing material is exposed to an extractant containing a liquid or supercritical-fluid solvent and an acid-base complex including an oxidizing agent and a complexing agent. Batches of the metal-containing material are moved through a series of stations while the extractant is moved through the stations in the opposite direction. After the extraction step, the metal is separated from the solvent, the complexing agent and/or other metals by exposing the extract to a stripping agent in a countercurrent stripping column. The complexing agent and the solvent exit the column and are separated from each other by reducing the pressure. The recovered complexing agent is recharged with fresh oxidizing agent and recombined with fresh or recovered solvent to form a recovered extractant, which is distributed through the extraction stations.

    摘要翻译： 公开了一种用于从含金属的材料中回收诸如铀的金属的方法和系统的实施例。 含金属材料暴露于含有液体或超临界流体溶剂的萃取剂和包含氧化剂和络合剂的酸碱络合物。 含金属材料的批次通过一系列工位移动，同时将萃取剂沿相反方向移动通过工位。 在提取步骤之后，通过将提取物暴露于逆流汽提塔中的汽提剂将金属与溶剂，络合剂和/或其它金属分离。 络合剂和溶剂离开塔并通过降低压力彼此分离。 回收的络合剂用新鲜的氧化剂再充电并与新鲜或回收的溶剂重新组合以形成回收的萃取剂，其通过萃取站分配。

    Sodium salt recycling process for use in wet reprocessing process of spent nuclear fuel
    26.
    发明授权
    Sodium salt recycling process for use in wet reprocessing process of spent nuclear fuel 有权
    用于乏核燃料的湿再加工过程的钠盐回收工艺

    公开(公告)号：US07666370B2

    公开(公告)日：2010-02-23

    申请号：US12087288

    申请日：2007-01-15

    申请人： Yoshinobu Takaoku ,  Yukio Sumida ,  Noriyasu Moriya

    发明人： Yoshinobu Takaoku ,  Yukio Sumida ,  Noriyasu Moriya

    IPC分类号： B01D11/00 ,  G21F9/00 ,  G21F9/16 ,  G21F9/20

    CPC分类号： G21C19/46 ,  G21F9/125 ,  Y02W30/883

    摘要： The present disclosure relates to a process for recycling a sodium salt by decomposition of a sodium nitride liquid waste, comprising a neutralization step in which a nitric acid liquid waste or an off-gas having nitric acid dissolved therein which is produced through a wet reprocessing process comprising a dissolution step for dissolving a spent nuclear fuel in nitric acid is neutralized by adding or contacting the nitrate liquid waste or the off-gas to or with at least one sodium salt selected from the group consisting of sodium hydroxide, sodium hydrogencarbonate and sodium carbonate, thereby yielding a sodium nitrate liquid waste; a sodium nitrate-decomposition step in which the sodium nitrate liquid waste is reductively decomposed with a reducing agent, thereby decomposing sodium nitrate into a nitrogen gas and the sodium salt; and a recycle step for recycling the sodium salt into the neutralization step or wet reprocessing process.

    摘要翻译： 本公开涉及通过氮化钠液体废物分解再循环钠盐的方法，其包括中和步骤，其中通过湿再加工过程产生硝酸液体废物或其中溶解有硝酸的废气 包括用于将废核燃料溶解在硝酸中的溶解步骤，通过向硝酸液体废物或废气中加入或接触至少一种选自氢氧化钠，碳酸氢钠和碳酸钠的钠盐而中和 ，从而产生硝酸钠液体废物; 硝酸钠分解步骤，其中硝酸钠液体废物用还原剂还原分解，从而将硝酸钠分解成氮气和钠盐; 以及将钠盐再循环到中和步骤或湿再加工过程中的再循环步骤。

    SPENT FUEL REPROCESSING METHOD
    27.
    发明申请
    SPENT FUEL REPROCESSING METHOD 审中-公开
    空气燃料代用方法

    公开(公告)号：US20090294299A1

    公开(公告)日：2009-12-03

    申请号：US12470226

    申请日：2009-05-21

    申请人： Koji MIZUGUCHI ,  Reiko FUJITA ,  Kouki FUSE ,  Hitoshi NAKAMURA ,  Kazuhiro Utsunomiya ,  Akihiro KAWABE

    发明人： Koji MIZUGUCHI ,  Reiko FUJITA ,  Kouki FUSE ,  Hitoshi NAKAMURA ,  Kazuhiro Utsunomiya ,  Akihiro KAWABE

    IPC分类号： C25C1/22 ,  C25B1/00

    CPC分类号： G21C19/46 ,  C25C1/22 ,  C25C3/34 ,  Y02P10/212 ,  Y02W30/883

    摘要： A spent fuel reprocessing method has a dissolution step of dissolving the spent fuel in nitric acid solution, an electrolysis/valence adjustment step of reducing Pu to trivalent, maintaining the pentavalent of Np, a uranium extraction step of collecting UO2 by bringing the fuel into contact with organic solvent and extracting hexavalent U by means of an extraction agent, an oxalic acid precipitation step of causing MA and the fissure products remaining in the nitric acid solution to precipitate together as oxalic acid precipitate, a chlorination step of converting the oxalic acid precipitate into chlorides by adding hydrochloric acid to the oxalic acid precipitate, a dehydration step of synthetically producing anhydrous chlorides by dehydrating the chlorides in a flow of Ar gas, and a molten salt electrolysis step of dissolving the anhydrous chlorides into molten salt and collecting U, Pu and MA at the cathode by electrolysis.

    摘要翻译： 废燃料后处理方法具有将废燃料溶解在硝酸溶液中的溶解步骤，将Pu还原成三价的电解/化合价调节步骤，维持Np的五价，通过使燃料接触而进行收集UO2的铀萃取步骤 用有机溶剂，通过萃取剂萃取六价U，草酸沉淀步骤使草酸残留在硝酸溶液中沉淀在一起沉淀，草酸沉淀步骤将草酸沉淀物转化为 通过向草酸沉淀中加入盐酸的氯化物，通过在Ar气流中使氯化物脱水合成生产无水氯化物的脱水步骤，以及熔融盐电解步骤，将无水氯化物溶解在熔融盐中并收集U，Pu和 MA通过电解在阴极。

    Method and System for Recovering Metal from Metal-Containing Materials
    28.
    发明申请
    Method and System for Recovering Metal from Metal-Containing Materials 有权
    含金属材料回收金属的方法与系统

    公开(公告)号：US20080134837A1

    公开(公告)日：2008-06-12

    申请号：US11795424

    申请日：2006-01-12

    申请人： Chien M. Wai ,  Sydney S. Koegler

    发明人： Chien M. Wai ,  Sydney S. Koegler

    IPC分类号： C22B60/02 ,  C22B60/04

    CPC分类号： C01G43/003 ,  B01D11/0203 ,  B01D11/0284 ,  B01D11/0288 ,  B01D11/0292 ,  C01P2006/80 ,  C22B3/0005 ,  C22B3/02 ,  C22B60/0239 ,  C22B60/026 ,  C22B60/04 ,  G21C19/46 ,  Y02P10/234 ,  Y02P20/544 ,  Y02W30/883

    摘要： Embodiments of a method and a system for recovering a metal, such as uranium, from a metal-containing material are disclosed. The metal-containing material is exposed to an extractant containing a liquid or supercritical-fluid solvent and an acid-base complex including an oxidizing agent and a complexing agent. Batches of the metal-containing material are moved through a series of stations while the extractant is moved through the stations in the opposite direction. After the extraction step, the metal is separated from the solvent, the complexing agent and/or other metals by exposing the extract to a stripping agent in a countercurrent stripping column. The complexing agent and the solvent exit the column and are separated from each other by reducing the pressure. The recovered complexing agent is recharged with fresh oxidizing agent and recombined with fresh or recovered solvent to form a recovered extractant, which is distributed through the extraction stations.

    摘要翻译： 公开了一种用于从含金属的材料中回收诸如铀的金属的方法和系统的实施例。 含金属材料暴露于含有液体或超临界流体溶剂的萃取剂和包含氧化剂和络合剂的酸碱络合物。 含金属材料的批次通过一系列工位移动，同时将萃取剂沿相反方向移动通过工位。 在提取步骤之后，通过将提取物暴露于逆流汽提塔中的汽提剂将金属与溶剂，络合剂和/或其它金属分离。 络合剂和溶剂离开塔并通过降低压力彼此分离。 回收的络合剂用新鲜的氧化剂再充电并与新鲜或回收的溶剂重新组合以形成回收的萃取剂，其通过萃取站分配。

    Process for the dissolution of actinic oxides
    29.
    发明申请
    Process for the dissolution of actinic oxides 失效
    光化学氧化物溶解方法

    公开(公告)号：US20060110303A1

    公开(公告)日：2006-05-25

    申请号：US10528905

    申请日：2003-09-26

    申请人： Peter Johathan Rance ,  Robert Bernard

    发明人： Peter Johathan Rance ,  Robert Bernard

    IPC分类号： C22B60/02

    CPC分类号： G21C19/46 ,  G21F9/30 ,  Y02W30/883

    摘要： The invention provides a process for dissolving actinic oxides, the process comprising performing the steps of (a) introducing the actinic oxides into a solution of nitric acid; (b) treating the acidic solution in order to substantially remove palladium; and (c) treating with divalent silver. Preferably, the actinic oxides are comprised in spent nuclear fuel. Optionally, the process comprises a second treatment of the acidic solution in order to substantially remove palladium and a second treatment with divalent silver. The steps may be performed on a batchwise or continuous basis. The treatment to remove palladium is preferably carried out by solvent extraction or ion exchange, and provides greatly improved rates of dissolution of oxides of plutonium. The treatment with divalent silver preferably involves the addition of a source of monovalent silver, followed by an electrolysis treatment to generate divalent silver.

    摘要翻译： 本发明提供了一种溶解光化学氧化物的方法，该方法包括以下步骤：（a）将光化学氧化物引入硝酸溶液中; （b）处理酸性溶液以便基本上除去钯; 和（c）用二价银处理。 优选地，光化学氧化物包含在乏核燃料中。 任选地，该方法包括酸性溶液的第二次处理以便基本上除去钯和用二价银进行第二次处理。 步骤可以在间歇或连续的基础上进行。 去除钯的处理优选通过溶剂萃取或离子交换进行，并提供大大提高的钚氧化物溶解速率。 二价银的处理优选包括添加一价银源，随后进行电解处理以产生二价银。

    Nuclear fuel reprocessing
    30.
    发明授权
    Nuclear fuel reprocessing 失效
    核燃料后处理

    公开(公告)号：US06623710B1

    公开(公告)日：2003-09-23

    申请号：US09530825

    申请日：2000-09-29

    申请人： Emmanuel Gaubert ,  Gavin Paul Towler ,  Andrew Lindsay Wallwork

    发明人： Emmanuel Gaubert ,  Gavin Paul Towler ,  Andrew Lindsay Wallwork

    IPC分类号： C22B6000

    CPC分类号： G21C19/46 ,  Y02W30/883

    摘要： A spent fuel reprocessing method including the steps of partitioning U and Pu(III) in a solvent by solvent extraction and subsequently polishing the solvent in a neptunium rejection operation for removing Np therefrom. The solvent obtained from the neptunium rejection operation (the polished solvent or NpA solvent product) is then recycled to a U/Pu partitioning operation. The method enables a reduction in solvent feed and solvent effluent volumes.

    摘要翻译： 一种乏燃料后处理方法，包括以下步骤：通过溶剂萃取在溶剂中分配U和Pu（III），随后在去除Np的Neptunium排除操作中抛光溶剂。 然后将从Neptunium排除操作获得的溶剂（抛光溶剂或NpA溶剂产物）再循环至U / Pu分配操作。 该方法能够降低溶剂进料和溶剂流出物体积。