Method of producing sulfur tetrafluoride from uranium tetrafluoride
    1.
    发明授权
    Method of producing sulfur tetrafluoride from uranium tetrafluoride 失效
    从四氟化铀生产四氟化硫的方法

    公开(公告)号:US08367026B2

    公开(公告)日:2013-02-05

    申请号:US12916276

    申请日:2010-10-29

    Abstract: A method for converting depleted uranium tetrafluoride (UF4) to triuranium octaoxide (U3O8), and producing sulfur tetrafluoride, using a two step process. The first step uses heat and a mixture of the uranium tetrafluoride and an alkaline compound, either an alkaline oxide or an alkaline hydroxide, to produce U3O8 and a water-soluble metal halide. The second step uses heat, sulfur and a halogen to produce sulfur tetrafluoride and triuranium octaoxide.

    Abstract translation: 使用两步法将贫铀四氟化铀(UF4)转化为三氧化铀(U3O8)并生产四氟化硫的方法。 第一步使用热和四氟化铀与碱性化合物(碱性氧化物或碱性氢氧化物)的混合物来制备U 3 O 8和水溶性金属卤化物。 第二步使用热,硫和卤素来产生四氟化硫和三氧化铀八氧化物。

    Method of treating gas based on electrolytic fluorine containing uranium
compounds
    2.
    发明授权
    Method of treating gas based on electrolytic fluorine containing uranium compounds 失效
    基于电解氟铀化合物处理气体的方法

    公开(公告)号:US5284605A

    公开(公告)日:1994-02-08

    申请号:US850883

    申请日:1992-03-13

    Inventor: Francois Nicolas

    CPC classification number: B01D53/68 B01D53/002 C01G43/066 Y02C20/30 Y10S62/918

    Abstract: A method of treating a gas based on fluorine and containing hydrofluoric acid, and which may optionally contain condensable gaseous compounds, especially uranium compounds, and non-condensable gases. The gas is refrigerated to obtain a gaseous component containing fluorine and any non-condensable gases present, and a liquid phase containing liquid HF and condensable compounds in solution and/or suspension. The liquid phase is filtered to recover the compounds in suspension.

    Abstract translation: 一种处理基于氟并含有氢氟酸的气体的方法,其可任选地包含可冷凝气态化合物,特别是铀化合物和不可冷凝气体。 将气体冷却以获得含有氟和存在的任何不可冷凝气体的气态组分,以及在溶液和/或悬浮液中含有液体HF和可冷凝化合物的液相。 过滤液相以回收悬浮液中的化合物。

    Multichamber type fluid bed reaction apparatus and method
    3.
    发明授权
    Multichamber type fluid bed reaction apparatus and method 失效
    多室型流化床反应装置及方法

    公开(公告)号:US5264196A

    公开(公告)日:1993-11-23

    申请号:US892658

    申请日:1992-06-03

    CPC classification number: B01J8/36 C01G43/066

    Abstract: A multichamber type fluid bed reaction apparatus has a series of chambers formed by dividing the fluid bed part and the wind box part thereof with particular walls. Each reaction chamber is supplied with a reaction gas whose composition, flow amount and temperature can be selected arbitrarily. A fluid bed, a moving bed or a fixed bed may be used in each divided chamber. Regulation of particle formation, gas-particle reaction and amount of particles transferring between the chambers results in an improvement of efficiency and a simplification of the apparatus.

    Abstract translation: 多室型流化床反应装置具有通过将流化床部分和其风箱部分分隔成特定壁而形成的一系列室。 向每个反应室供应反应气体,其组成,流量和温度可任意选择。 在每个分隔室中可以使用流化床,移动床或固定床。 颗粒形成,气体 - 颗粒反应和颗粒在室之间转移的量的调节导致效率的提高和设备的简化。

    Method for reducing uranium tetrafluoride
    4.
    发明授权
    Method for reducing uranium tetrafluoride 失效
    减少四氢呋喃的方法

    公开(公告)号:US4051227A

    公开(公告)日:1977-09-27

    申请号:US700377

    申请日:1976-06-28

    Applicant: Henry M. Heidt

    Inventor: Henry M. Heidt

    CPC classification number: C01G43/066 C01G43/025 C01P2004/61

    Abstract: A pulsed flow process for the reduction of UF.sub.6 where the process may be continuous or batch starting without a seed bed. The initial amplitude and frequency of the pulsed flow is altered as a bed of particle-form material is formed and thereafter the particle-form product of the reaction is removed from the reaction zone.

    Irradiated fuel reprocessing
    5.
    发明授权
    Irradiated fuel reprocessing 失效
    辐射燃料代替

    公开(公告)号:US4011296A

    公开(公告)日:1977-03-08

    申请号:US581138

    申请日:1975-05-27

    CPC classification number: C01G43/066 C01G56/001 G21C19/46 G21F9/007 Y02W30/883

    Abstract: A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium.

    Method for preparing high purity 233 uranium
    6.
    发明授权
    Method for preparing high purity 233 uranium 失效
    制备高纯度233铀的方法

    公开(公告)号:US3714322A

    公开(公告)日:1973-01-30

    申请号:US3714322D

    申请日:1970-06-10

    Inventor: BELL M WHATLEY M

    CPC classification number: G21F9/007 C01G43/066 C22B60/0286

    Abstract: A method for preparing high purity 233uranium is provided by processing molten salt reactor fuels containing protactinium isotopes in a series of at least two hold-up tanks wherein in the first tank, decay of 232protactinium to 232uranium is permitted to a preselected value and the 232uranium is removed by subsequent fluorination. In the second tank, decay of 233protactinium to 233uranium is permitted to a preselected value and the 233uranium, which is highly depleted in 232uranium, is recovered by subsequent fluorination.

    Abstract translation: 通过在一系列至少两个滞留槽中加工含有铀同位素的熔盐反应堆燃料来提供制备高纯度233的方法,其中在第一罐中,允许将232盎司到232铀的衰变为预选值,并且232铀 通过随后的氟化除去。 在第二个槽中,将233个钚的朽烂允许为233个预定值,并且通过随后的氟化回收233铀,其高度耗尽了232铀。

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