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    Method for treating a particulate nuclear fuel material
    2.
    发明授权
    Method for treating a particulate nuclear fuel material 失效
    颗粒状核燃料材料的处理方法

    公开(公告)号：US4234550A

    公开(公告)日：1980-11-18

    申请号：US739716

    申请日：1976-11-08

    申请人： William R. DeHollander

    发明人： William R. DeHollander

    IPC分类号： C01G43/025 ,  C01G43/02

    CPC分类号： C01G43/025 ,  C01P2004/32 ,  C01P2004/50 ,  C01P2006/10

    摘要： A process for treating a particulate uranium oxide composition containing ammonium diuranate precursors such as uranyl fluoride and uranyl nitrate, along with possible impurities, is disclosed. The process comprises the steps of (a) contacting the composition with a sufficient amount of an ammonium hydroxide solution to convert the ammonium diuranate precursors to ammonium diuranate, and (b) heating the composition under a controlled atmosphere at a temperature sufficient to dry the composition, sublime any ammonium fluoride present, and convert the ammonium diuranate to uranium dioxide. In a first modification of the invention, there is practiced the additional step of moving the composition, preferably by mechanically agitating the composition, prior to the heating step, or during the heating step, or both prior to and during the heating step, for a sufficient time to produce rounded agglomerates in the form of a readily flowable powder. In another modification of the invention, there are practiced the additional steps of mechanically agitating the composition and screening the composition prior to heating. These additional steps produce rounded agglomerates of the composition in a desired size distribution.

    摘要翻译： 公开了一种用于处理含有二氢铀酸铵前体如铀氧氟化物和硝酸铀酰的颗粒状铀氧化物组合物以及可能的杂质的方法。 该方法包括以下步骤：（a）使组合物与足够量的氢氧化铵溶液接触以将二异丙酸铵前体转化成二氢化铵铵，和（b）在足以干燥组合物的温度下在受控气氛下加热该组合物 ，使任何氟化铵存在，并将二氢阿魏酸铵转化为二氧化铀。 在本发明的第一修改中，实施了在加热步骤之前，或在加热步骤期间，或者在加热步骤之前和加热步骤期间两者均优选地通过机械搅拌组合物来移动组合物的附加步骤 有足够的时间生产易流动粉末形式的圆形团块。 在本发明的另一变型中，实施了在加热之前机械搅拌组合物并筛选组合物的附加步骤。 这些附加步骤以期望的尺寸分布产生组合物的圆形团聚体。

    Crown ether uranyl halide complexes
    3.
    发明授权
    Crown ether uranyl halide complexes 失效
    冠醚铀酰卤络合物

    公开(公告)号：US4186175A

    公开(公告)日：1980-01-29

    申请号：US872144

    申请日：1978-01-25

    申请人： David L. Tomaja

    发明人： David L. Tomaja

    IPC分类号： B01J19/12 ,  C01G43/01 ,  C01G43/08 ,  C07F5/00 ,  C22B3/26 ,  C22B60/02 ,  B01J1/10 ,  C01G43/02 ,  C07D323/00

    CPC分类号： C22B60/026 ,  B01J19/122 ,  C01G43/01 ,  C01G43/08 ,  C07F5/003 ,  C22B3/002 ,  Y02P10/234

    摘要： Uranium oxide is recovered from an aqueous solution of uranyl halides by extracting uranyl halide from the aqueous solution with an organic liquid, forming a crown ether uranyl halide complex in the organic liquid, and then contacting the uranyl halide crown ether complex with water, carboxylate ion, and light under suitable conditions. Also disclosed are certain novel crown ether uranyl halide complexes and their preparation. Also disclosed is the use of 18-crown-6 to selectively recover uranyl halide from a solution thereof containing other metal salts.

    摘要翻译： 通过用有机液体从水溶液中提取铀酰卤，从有机液体中形成冠醚铀酰卤配合物，然后将铀酰卤化物冠醚配合物与水，羧酸根离子接触，从铀酰卤水溶液中回收氧化铀 ，并在合适的条件下进行光照。 还公开了某些新型冠醚铀酰卤络合物及其制备方法。 还公开了使用18-冠-6从其含有其它金属盐的溶液中选择性回收铀酰卤化物。

    Method of fabrication of uranium oxide UO.sub.2 by the dry processing route and a device for the practical application of the method
    4.
    发明授权
    Method of fabrication of uranium oxide UO.sub.2 by the dry processing route and a device for the practical application of the method 失效
    氧化铀UO {HD2 {B通过干法处理途径和实际应用该方法的装置）的制造方法

    公开(公告)号：US4112055A

    公开(公告)日：1978-09-05

    申请号：US682747

    申请日：1976-05-03

    申请人： Robert Artaud

    发明人： Robert Artaud

    IPC分类号： C01G43/025 ,  C01G43/02 ,  C01G43/06

    CPC分类号： C01G43/025 ,  C01P2004/61 ,  C01P2004/62 ,  C01P2006/10 ,  C01P2006/12 ,  C01P2006/80

    摘要： In a first step, uranium hexafluoride gas is reacted with steam in a first region of a vessel. In a second step, the oxyfluoride UO.sub.2 F.sub.2 obtained in the first step is converted to UO.sub.2 in a two-stage reduction process in which it is first contacted with a mixture of hydrogen gas and steam in one zone of the second region of the vessel, then contacted with the hydrogen gas in another zone of the second region.

    摘要翻译： 在第一步骤中，六氟化铀气体与容器的第一区域中的蒸汽反应。 在第二步中，将第一步中获得的氟氧化物UO2F2在二级还原过程中转化为UO2，其中它首先在容器的第二区域的一个区域中与氢气和蒸汽的混合物接触，然后 与第二区域的另一区域中的氢气接触。

    Process for producing uranium oxide rich compositions from uranium hexafluoride using fluid injection into the reaction zone
    5.
    发明授权
    Process for producing uranium oxide rich compositions from uranium hexafluoride using fluid injection into the reaction zone 失效
    使用流体注入反应区，从六氟化铀生产富铀的组合物的方法

    公开(公告)号：US4031029A

    公开(公告)日：1977-06-21

    申请号：US592508

    申请日：1975-07-02

    申请人： John Cecil Colter ,  Dean B. James ,  Walter Gill Keith ,  Reza Akbari-Kenari

    发明人： John Cecil Colter ,  Dean B. James ,  Walter Gill Keith ,  Reza Akbari-Kenari

    IPC分类号： C01G43/01 ,  C01G43/025 ,  C01G43/02

    CPC分类号： C01G43/01 ,  C01G43/025

    摘要： An improved process for the conversion of gaseous uranium hexafluoride to a uranium oxide rich composition in the presence of an active flame in a reaction zone is achieved by introducing a first gaseous reactant comprising a mixture of uranium hexafluoride and an oxygen-containing carrier gas and a second gaseous reactant comprising a reducing gas, the reactants being separated by a shielding gas as introduced to the reaction zone. The shielding gas temporarily separates the gaseous reactants and temporarily prevents substantial mixing and reacting of the gaseous reactants. The flame occurring in the reaction zone is maintained away from contact with the inlet introducing the mixture to the reaction zone. The process also includes introducing an oxygen-containing gas as a third gaseous reactant at a time when the uranium hexafluoride conversion to uranium dioxide is substantially complete resulting in oxidizing the uranium oxide composition to a higher oxide of uranium and conversion of the residual reducing gas to its oxidized form. During the process there is practiced the improvement of introducing an atomized fluid having a high latent heat of evaporation so that the atomized fluid directly enters the reaction zone and the introduction can be made at a location so that the atomized fluid enters the primary flame, the secondary flame, or both the primary and secondary flames, or downstream from the secondary flame. The atomized fluid can be introduced alone or with a carrier gas such as an oxygen-containing gas.

    摘要翻译： 通过引入包含六氟化铀和含氧载气的混合物的第一气态反应物和一种含氧载体气体来实现在活性火焰存在下在反应区中将气态六氟化铀转化为富含氧化铀的组合物的改进方法 第二气态反应物包含还原气体，反应物被引入反应区的保护气体分离。 保护气体暂时分离气态反应物，并暂时防止气态反应物的大量混合和反应。 在反应区中发生的火焰保持远离与将混合物引入反应区的入口接触。 该方法还包括在六氟化铀转化为二氧化铀基本上完成时引入含氧气体作为第三气态反应物，从而将铀氧化物组合物氧化成较高的铀氧化物，并将残余的还原气体转化为 其氧化形式。 在该过程中，实施了引入具有高蒸发潜热的雾化流体的改进，使得雾化的流体直接进入反应区，并且可以在一个位置进行引入，使得雾化流体进入主火焰， 二次火焰，或主要和次要火焰，或次要火焰的下游。 雾化的流体可以单独引入或与载气如含氧气体一起引入。

    Fluidized reactor reduction of UF{HD 6 {B to UO{HD 2
    6.
    发明授权
    Fluidized reactor reduction of UF{HD 6 {B to UO{HD 2 失效
    UF的流化反应器减少{HD 6 {B至UO {HD 2

    公开(公告)号：US3906081A

    公开(公告)日：1975-09-16

    申请号：US36550873

    申请日：1973-05-31

    申请人： EXXON NUCLEAR CO INC

    发明人： WELTY RICHARD K

    IPC分类号： C01G43/01 ,  C01G43/025 ,  C01G43/02

    CPC分类号： C01G43/01 ,  C01G43/025

    摘要： A two stage fluid bed process for converting UF6 to UO2 is provided. In the first stage UF6 is converted, preferably in two separate fluid beds, to U3O8 by first forming UO2F2 solids and treating the UO2F2 with steam to produce U3O8. The U3O8 is reduced at relatively low temperatures i.e., at about 450*C. to about 500*C., in a second stage to uranium dioxide.

    摘要翻译： 提供了一种用于将UF6转化为UO2的两阶段流化床工艺。 在第一阶段中，UF6优选在两个单独的流化床中通过首先形成UO2F2固体并用蒸汽处理UO2F2以产生U3O8而转化成U3O8。 U 3 O 8在相对较低的温度下，即在约450℃至约500℃，在第二阶段中还原成二氧化铀。

    Conversion of uranium hexafluoride to uranium dioxide structures of controlled density and grain size
    7.
    发明授权
    Conversion of uranium hexafluoride to uranium dioxide structures of controlled density and grain size 失效
    乌司他丁转化为二氧化碳控制密度和颗粒尺寸的二氧化硫结构

    公开(公告)号：US3819804A

    公开(公告)日：1974-06-25

    申请号：US15374971

    申请日：1971-06-16

    申请人： GEN ELECTRIC

    发明人： DEHOLLANDER W R

    IPC分类号： C01G43/025 ,  G21C3/62 ,  C01G43/02

    CPC分类号： C01G43/025 ,  C01P2004/62 ,  C01P2006/10 ,  C01P2006/80 ,  G21C3/623 ,  Y02E30/38

    摘要： AN INTEGRATED PROCESS FOR FIBRICATING URANIUM DIOXIDE STRUCTURES OF DESIRED SHAPE, DENSITY AND GRAIN SIZE FROM ENRICHED URANIUM HEXAFLUORIDE IS PRESENTED. URANIUM HEXAFLUORIDE IS REACTED WITH A REDUCING GAS AND AN OXYGENCONTAINING CARRIER GAS IN A REDUCTION-HYDROLYSIS REACTION IN AN ACTIVE FLAME TO YEILD A URANIUM DIOXIDE RICH POWDER OF HIGH SURFACE AREA WITH FLUORIDE IMPURITIES. THE POWDER IS SEPARATED FROM THE GAS STREAM AFTER THE REACTION AND IS PREPRESSED TO A GIVEN SHAPE BY APPLICATION OF PRESSURE AND THEN BROKEN INTO FREE FLOWING PARTICLES OF A SELECTED SIZE RANGE BY GRANULATION. PARTICLES OF POWDER OUTSIDE THE SELECTED SIZE RANGE ARE SCREENED OUT AND CAN BE COMBINED WITH SUBSEQUENT POWDER PRODUCTION FOR PREPRESSING. THE GRANULATED POWDER IS DEFLUORINATED BY HEATING UNDER A CONTROLLED ATMOSPHERE SO THAT THE HIGH SURFACE AREA OF THE POWDER IS PRESERVED. THE DEFLUORINATED POWDER IS THEN PRESSED INTO A STRUCTURE OF DESIRE SHAPE AND SINTERED UNDER A CONTROLLED ATMOSPHERE TO YIELD A CERAMIC STRUCTURE OF DESIRED DENSITY AND GRAIN SIZE. THE GAS STREAM FROM THE REACTION OF THE URANIUM HEXAFLUORIDE IS TREATED TO CONDENSE THE HYDROGEN FLUORIDE AND WATER VAPOR AS AQUEOUS HYDROFLUORIDE ACID. THE PROCESS OF THIS INVENTION CAN BE USED WITH OXIDES OF URANIUM OF HIGH SURFACE AREA IN ANY STATE OF OXIDATION FROM URANIUM DIOXIDE (UO2) TO URANIUM TRITAOCTOXIDE (U3O8) INCLUDING OXIDES PRODUCED BY A POST OXIDATION PROCESS CONVERTING THE URANIUM DIOXIDE RICH POWDER TO THE HIGHER OXIDE OF URANIUM.

    Method of preparing relatively low density oxide fuel for a nuclear reactor
    8.
    发明授权
    Method of preparing relatively low density oxide fuel for a nuclear reactor 失效
    为核反应堆制备相对低密度氧化物燃料的方法

    公开(公告)号：US3806565A

    公开(公告)日：1974-04-23

    申请号：US16845371

    申请日：1971-08-02

    申请人： NORTH AMERICAN ROCKWELL

    发明人： LANGROD K

    IPC分类号： G21C3/62 ,  G21C3/04 ,  C01G43/02 ,  G21C21/02

    CPC分类号： G21C3/623 ,  Y02E30/34 ,  Y02E30/38 ,  Y10S376/901

    摘要： A method of preparing an oxide fuel for a nuclear reactor in which uranium dioxide powder or an intimate mixture of uranium dioxide and plutonium dioxide or thorium dioxide powders is sintered, the sintered material is comminuted to a fine powder, the fine powder is compacted by cold pressing and the compact is resintered at approximately the same temperature used for the first sintering.

    摘要翻译： 制备其中二氧化dioxide dioxide powder is is is onium onium cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold cold 压制，并且压块在用于第一次烧结的大致相同的温度下重新烧结。