Sodium Salt Recycling Process for Use in Wet Reprocessing Process of Spent Nuclear Fuel
    1.
    发明申请
    Sodium Salt Recycling Process for Use in Wet Reprocessing Process of Spent Nuclear Fuel 有权
    用于废核燃料的湿再加工过程中的钠盐回收方法

    公开(公告)号:US20090068075A1

    公开(公告)日:2009-03-12

    申请号:US12087288

    申请日:2007-01-15

    CPC classification number: G21C19/46 G21F9/125 Y02W30/883

    Abstract: The present invention is directed to a process for recycling of a sodium salt by decomposition of a sodium nitride liquid waste. The process comprises: 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 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. The sodium nitrate liquid waste obtained in the neutralization step may be concentrated by evaporation to give a concentrated sodium nitrate liquid waste, and the condensed sodium nitrate liquid waste may be reductively decomposed in the sodium nitrate-decomposition step.

    Abstract translation: 本发明涉及一种通过分解氮化钠液体废物再循环钠盐的方法。 该方法包括:中和步骤,其中通过包括用于将废核燃料溶解在硝酸中的溶解步骤的湿再加工过程产生的硝酸液体废物或其中溶解有硝酸的废气通过加入或 将硝酸液体废物或废气与至少一种选自氢氧化钠,碳酸氢钠和碳酸钠的钠盐接触或与其接触,从而产生硝酸钠废液; 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。 在中和步骤中获得的硝酸钠废液可以通过蒸发浓缩,得到浓硝酸钠废液,并且在硝酸钠分解步骤中还原硝酸钠废液可被还原分解。

    FUSION PROCESS USING AN ALKALI METAL METALATE
    3.
    发明申请
    FUSION PROCESS USING AN ALKALI METAL METALATE 有权
    使用碱金属金属的熔融过程

    公开(公告)号:US20080226528A1

    公开(公告)日:2008-09-18

    申请号:US11952335

    申请日:2007-12-07

    Abstract: The product of a molten alkali metal metalate phase separation can be processed into a purified metal from a metal source. Metal sources include native ores, recycled metal, metal alloys, impure metal stock, recycle materials, etc. The method uses a molten alkali metal metalate as a process medium or solvent in purifying or extracting high value metal or metal oxides from metal sources. Vitrification methods using the silicate glass separation phase can be prepared as is or can be prepared with a particulate phase distributed throughout the silica glass phase and encapsulated and fixed within the continuous glass phase. Tungsten metal can be obtained from an alkali metal tungstate. A typically finely divided tungsten metal powder can be obtained from a variety of tungsten sources including recycled tungsten scrap, tungsten carbide scrap, low grade tungsten ore typically comprising tungsten oxide or other form of tungsten in a variety of oxidation states.

    Abstract translation: 熔融碱金属金属相分离的产物可以从金属源加工成纯化的金属。 金属源包括天然矿石,回收金属,金属合金,不纯金属原料,回收材料等。该方法使用熔融碱金属金属盐作为从金属源净化或提取高价值金属或金属氧化物的工艺介质或溶剂。 使用硅酸盐玻璃分离相的玻璃化方法可以按原样制备,或者可以通过分布在整个石英玻璃相中的颗粒相制备并封装并固定在连续玻璃相中。 钨金属可以由碱金属钨酸盐获得。 可以从各种钨源获得通常细分的钨金属粉末,包括回收的废钨,碳化钨废料,通常包含氧化钨或其它各种氧化态的钨的其它形式的钨的低品位钨矿。

    Generator and Method for Production of Technetium-99m
    4.
    发明申请
    Generator and Method for Production of Technetium-99m 审中-公开
    锝-99m的发电机和生产方法

    公开(公告)号:US20080187489A1

    公开(公告)日:2008-08-07

    申请号:US11665186

    申请日:2005-10-06

    CPC classification number: C01G99/006 C01P2006/80 C01P2006/88 G21G1/00 G21G4/08

    Abstract: A generator that allows for a non-fission based method of producing and recovering 99mTc from neutron-irradiated molybdenum. This generator system is based on the isolation of 99mTc, as the decay product from a source of 99Mo labelled molybdenum carbonyl Mo(CO)6 through a distillation process. The 99mTc obtained from this distillation is produced with high efficiency and purity in a solvent-free form, which can then be dissolved in water or other solvents to produce a solution at the required specific activity and concentration, as reasonably determined by the operator.

    Abstract translation: 允许从中子照射的钼生产和回收99m Tc的基于非裂变的方法的发生器。 该发生器系统基于99m Tc的分离,作为来自99ppm Mo标记的钼羰基Mo(CO)6 N的源的衰变产物 >通过蒸馏过程。 从该蒸馏获得的99m Tc以无溶剂形式高效纯度地制备,然后将其溶解在水或其它溶剂中以产生所需比活度和浓度的溶液, 由操作员合理确定。

    Ceramicrete stabilization of U-and Pu-bearing materials
    5.
    发明授权
    Ceramicrete stabilization of U-and Pu-bearing materials 有权
    U型和Pu轴承材料的陶瓷混凝土稳定性

    公开(公告)号:US07294291B2

    公开(公告)日:2007-11-13

    申请号:US10782278

    申请日:2004-02-18

    Abstract: A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated by adjusting the pH of the nuclear material to not less than about 5 and adding sufficient MgO to convert fluorides present to MgF2; alumina is added in an amount sufficient to absorb substantially all hydrocarbon liquid present, after which a binder including MgO and KH2PO4 is added to the treated nuclear material to form a slurry. Additional MgO may be added. A crystalline radioactive material is also disclosed having a binder of the reaction product of calcined MgO and KH2PO4 and a radioactive material of the oxides and/or halides of actinides and/or transuranics (TRUs). Acids contaminated with actinides and/or TRUs, and/or actinides and/or TRUs with or without oils and/or greases may be encapsulated and stabilized by the binder.

    Abstract translation: 公开了一种稳定核材料的方法。 通过将核材料的pH调节至不小于约5并加入足够的MgO以转化氟化物来处理锕系元素和/或trans烷(TRU)和/或被锕系元素和/或TRU污染的烃和/或酸的氧化物或卤化物 存在于MgF 2上; 以足以吸收基本上所有存在的所有烃液体的量添加氧化铝,之后将包含MgO和KH 2 PO 4的粘合剂加入到经处理的核材料中以形成 泥浆。 可以加入另外的MgO。 还公开了一种结晶放射性材料,其具有煅烧的MgO和KH 2 PO 4的反应产物的粘合剂和锕系元素的氧化物和/或卤化物的放射性物质,以及 /或超ur(TRU)。 用锕系元素和/或TRU和/或锕系元素和/或具有或不含油和/或润滑脂的锕系元素和/或TRU污染的酸可以被粘合剂包封并稳定。

    Positive electrode active material, non-aqueous electrolyte secondary battery containing the same and method for evaluating positive electrode active material
    6.
    发明申请
    Positive electrode active material, non-aqueous electrolyte secondary battery containing the same and method for evaluating positive electrode active material 失效
    正极活性物质,含有该正极活性物质的非水电解质二次电池以及正极活性物质的评价方法

    公开(公告)号:US20050221182A1

    公开(公告)日:2005-10-06

    申请号:US11085040

    申请日:2005-03-22

    Abstract: A positive electrode active material powder for a non-aqueous electrolyte secondary battery, wherein an amount of a liquid reagent absorbed by the powder is 20 to 40 ml per 100 g of the powder when the liquid reagent is dibutyl phthalate, and the amount is 20 to 50 ml per 100 g of the powder when the liquid reagent is N-methyl-2-pyrrolidone or water, the absorption amount is a value measured using a device according to test method A or B regarding DBP absorption based on JIS K6217 (1997), and the measured value is an amount of the liquid reagent added until the viscosity of a mixture of the powder and the liquid reagent reaches a level corresponding to 70% of a maximum torque which is recorded when a change in the viscosity of a mixture of the powder and the liquid reagent is measured by a torque detecting device.

    Abstract translation: 一种非水电解质二次电池用正极活性物质粉末,其特征在于,液体试剂为邻苯二甲酸二丁酯时,粉末吸收的液体试剂的量为每100克粉末为20〜40ml,量为20 当液体试剂为N-甲基-2-吡咯烷酮或水时,每100克粉末至50毫升,吸收量是使用根据测试方法A或B的装置测量的关于基于JIS K6217(1997年)的DBP吸收的值 ),测定值为添加的液体试剂的量,直到粉末和液体试剂的混合物的粘度达到对应于混合物粘度变化时记录的最大扭矩的70%的水平 的粉末和液体试剂由扭矩检测装置测量。

    Method for heating and cooling slurries
    7.
    发明申请
    Method for heating and cooling slurries 失效
    加热和冷却浆料的方法

    公开(公告)号:US20050077032A1

    公开(公告)日:2005-04-14

    申请号:US10940893

    申请日:2004-09-13

    Inventor: Donald Donaldson

    Abstract: A system for cooling and recuperative heating of a slurry in a metallurgical process which includes heat exchangers, pumps and autoclaves is described herein. The heat exchangers use a non-scaling common liquid heat transfer medium. Preferably, the heat exchangers are tube-in-tube heat exchangers with 3 to 7 slurry tubes in each heat exchanger. An advantage of this system is that it does not use flash tanks. To minimize abrasive wear on impinged surfaces, the velocity of the slurry is not more than 5 meters per second. The slurry comprises a solids concentration of 25% to 50%. Preferably, the pumps in the system are float-type pumps in which the driven liquid from the discharge pumps is also used as the drive liquid for the feed pumps.

    Abstract translation: 本文描述了一种用于在包括热交换器,泵和高压釜的冶金工艺中的浆料的冷却和回热加热的系统。 热交换器使用不结垢的普通液体传热介质。 优选地,热交换器是在每个热交换器中具有3至7个浆料管的管内管式热交换器。 该系统的优点是不使用闪光灯。 为了最小化冲击表面的磨损,浆料的速度不超过5米/秒。 该浆料包含25%至50%的固体浓度。 优选地,系统中的泵是浮子式泵,其中来自排出泵的驱动液体也用作进料泵的驱动液体。

    Composition for growing laser crystals
    8.
    发明授权
    Composition for growing laser crystals 失效
    用于生长激光晶体的组成

    公开(公告)号:US5746991A

    公开(公告)日:1998-05-05

    申请号:US704469

    申请日:1996-08-23

    Inventor: Yoshinori Kubota

    CPC classification number: C30B15/00 C30B29/12

    Abstract: A composition for growing a laser crystal is represented by the formula of Li �R.sub.n .alpha..sub.1-n! �(Ga.sub.p In.sub.q) .beta..sub.1-p-q ! F.sub.6+n where n is within a range from 10.sup.-5 to 0.1, each of p and q is within a range from 0 to 0.6, a total of p and q is within a range from 0.001 to 0.6, .alpha. is at least one member selected from the group consisting of Ca, Sr, Ba and Na, .beta. is at least one member selected from the group consisting of Al, Cr, Ni, Co and Fe, and R is a rare-earth element. The composition enables the distribution coefficient of rare-earth element to get closer to 1 and thus enables the laser crystal to have a high and uniform concentration of rare-earth element and to have a large size.

    Abstract translation: 用于生长激光晶体的组合物由Li [Rnα1-n] [(Gap Inq)β1-pq] F6 + n的式表示,其中n在10-5至0.1的范围内,每个p q在0至0.6的范围内,p和q的总和在0.001至0.6的范围内,α是选自Ca,Sr,Ba和Na中的至少一种,β至少是 选自Al,Cr,Ni,Co和Fe中的一种,R是稀土元素。 该组合物能够使稀土类元素的分布系数接近1,能够使激光晶体具有高浓度且均匀的稀土元素浓度并具有大尺寸。

    Method of preparing a radiodiagnostic comprising a gaseous radionuclide,
as well as a radionuclide generator suitable for using said method
    9.
    发明授权
    Method of preparing a radiodiagnostic comprising a gaseous radionuclide, as well as a radionuclide generator suitable for using said method 失效
    制备包含气体放射性核素的放射性诊断的方法以及适用于使用所述方法的放射性核素发生器

    公开(公告)号:US5254328A

    公开(公告)日:1993-10-19

    申请号:US809559

    申请日:1992-01-23

    CPC classification number: G21G4/08

    Abstract: The invention relates to a method of preparing a radiodiagnostic comprising a gaseous radionuclide formed by radioactive decay of a parent nuclide, by eluting with a suitable eluent the radioactive daughter nuclide from the parent nuclide provided ionically on a carrier, by using as a carrier for the parent nuclide ions a membrane, in particular an ion exchange membrane, past which the eluent is made to flow.The invention further relates to a radionuclide generator suitable for using said method.

    Abstract translation: PCT No.PCT / US90 / 03897 Sec。 371日期1992年1月23日 102(e)日期1992年1月23日PCT 1990年7月11日PCT。本发明涉及一种制备放射诊断的方法,包括通过母体核素的放射性衰变形成的气体放射性核素,通过用合适的洗脱液洗脱放射性子 母体核素的核素通过离子性地在载体上提供,通过使用母体核素离子的载体,使膜(特别是离子交换膜)过去,使洗脱液流过。 本发明还涉及适用于所述方法的放射性核素发生器。

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