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    300-Year disposal solution for spent nuclear fuel
    22.
    发明申请
    300-Year disposal solution for spent nuclear fuel 审中-公开
    用于乏核燃料的300年处置解决方案

    公开(公告)号：US20080207977A1

    公开(公告)日：2008-08-28

    申请号：US11899209

    申请日：2007-09-04

    Applicant: William D. Peterson

    Inventor： William D. Peterson

    IPC: G21F9/00

    CPC classification number: G21F9/304 ,  G21F9/165 ,  G21F9/36

    Abstract: A method including a combination of intermediate storage and reprocessing is utilized to process spent nuclear fuel (SNF) and thereby effect a disposition of that SNF within a period of 300 years. The method includes five or more years of pool water storage wherein ninety-nine percent (%) of the fission wastes energy decays. The waste material is then stored in an air convention storage facility, before processing to separate Cesium and Strontium from the waste is effected. This air convection cooling may be done in convection air-cooled concrete casks. During 50 years of convection air-cooled storage the energy contained in the waste material declines another one half %. Thereafter, at any point the SNF is processed to sufficiently separate 99.999% of the 97% of actinides (approximately 95% U238 uranium, 1% U235 uranium, and 1% Pu239 plutonium) from the 3% fission wastes. Again, it is only necessary to provide approximately 99.999% separation of the TRU's (transuranic waste) from the fps (fission products)—more specifically, sufficient separation so that the residual fps are contaminated with less than 100 nCi/g TRU's, as defined in the Class C regulations—10CFR61. The separated actinides and transuranics are thereafter utilized in the manufacture of MOX (mixed oxide) or fast burner reactor fuel pellets for future reactor fuel. The remaining fission wastes, containing Cesium and Strontium, are then placed into containers and subsequently put into dry storage for the remainder of around 300 years, where most of the remaining half % of its radiation energy material, i.e., Cesium and Strontium decays. Thereafter this fission waste is put into a low level Class-C nuclear waste repository, which may include leaving them in the intermediate storage facility that is also designed to accommodate and dispose Class C waste.

    Abstract translation: 使用包括中间储存和再加工的组合的方法来处理乏燃料（SNF），从而在300年的时间内对该SNF的处置进行处理。 该方法包括五年或五年以上的池水储存，其中百分之九十九（％）的裂变废物能量衰减。 然后在将废弃物分离出铯和锶的处理之前将废料储存在空气会议存储设备中。 这种空气对流冷却可以在对流风冷混凝土桶中进行。 在50年的对流空冷存储中，废物中所含的能量下降了另外的一半。 此后，在任何时候处理SNF以从3％裂变废物中充分分离97％的锕系元素（约95％U238铀，1％U235铀和1％Pu239钚）的99.999％。 再次，仅需要从fps（裂变产物）提供大约99.999％的TRU（超铀废物）分离 - 更具体地说是足够的分离，使得剩余的fps被限定在少于100nCi / g TRU的范围内 在C级法规10CFR61。 此后分离的锕系元素和超铀元素用于制造未来反应堆燃料的MOX（混合氧化物）或快速燃烧器反应堆燃料颗粒。 剩余的含有铯和锶的裂变废物然后放置在容器中，随后放置在干燥储存中，剩余时间约为300年，其余的半数辐射能量材料的大部分即铯和锶都会衰变。 此后，这种裂变废物被放入一个低级别的C类核废料处理库中，这可能包括将它们留在中间储存设施中，该设施也被设计为容纳和处置C类废物。

    Apparatus for Nuclear Waste Disposal, Method for Manufacturing and Installing the Same
    23.
    发明申请
    Apparatus for Nuclear Waste Disposal, Method for Manufacturing and Installing the Same 审中-公开
    核废物处置装置，制造及安装其的方法

    公开(公告)号：US20080161628A1

    公开(公告)日：2008-07-03

    申请号：US11816115

    申请日：2006-02-13

    Applicant: Kyung Yeon Jo

    Inventor： Kyung Yeon Jo

    IPC: G21F1/04

    CPC classification number: G21F9/304

    Abstract: The present invention relates to a nuclear waste disposal apparatus, a method of manufacturing the same, and a method of installing the same. The apparatus is manufactured by packing nuclear waste into a vessel, installing the vessel into a ring-shaped elastic body such as a discarded tire used on a truck or a large-sized bus, covering the vessel storing the nuclear waste therein with high-strength reinforced concrete, and installing pieces of structural steel in a space of the elastic body so that the apparatus can endure heavy loads and natural disasters such as earthquakes.

    Abstract translation: 核废物处理装置及其制造方法技术领域本发明涉及核废物处理装置及其制造方法。 该装置通过将核废料包装在容器中而制造，将容器安装在诸如用于卡车或大型公共汽车上的废弃轮胎的环形弹性体中，覆盖其中存储有核废料的容器，具有高强度 钢筋混凝土，并将结构钢安装在弹性体的空间中，使得该装置能承受诸如地震的重载和自然灾害。

    Treatment of waste products
    24.
    发明申请
    Treatment of waste products 审中-公开
    废物处理

    公开(公告)号：US20050131265A1

    公开(公告)日：2005-06-16

    申请号：US10499283

    申请日：2002-12-20

    Applicant: Ian Godfrey ,  Martin Jowsey ,  Eric Miller

    Inventor： Ian Godfrey ,  Martin Jowsey ,  Eric Miller

    IPC: G21F9/30 ,  G21F9/00

    CPC classification number: G21F9/304

    Abstract: A method for the encapsulation of fine particulate materials includes treating these materials with a microfine hydraulic inorganic filler which, typically, includes a cementitious material, such as Portland Cement. The filler is ground to a much smaller particle size than is normally used in the production of a grout and is provided in the form of an aqueous composition for the treatment of the fine particulate materials by pumping under pressure through these materials such that they become intimately encapsulated. The method is particularly applicable to the treatment of waste materials and, most particularly, waste materials, which are encountered in the nuclear industry.

    Abstract translation: 用于包封细颗粒材料的方法包括用典型地包括水泥质材料如波特兰水泥的微细液压无机填料处理这些材料。 将填料研磨成比通常在生产水泥浆时常用的小得多的颗粒尺寸，并以水性组合物的形式提供，用于通过在压力下通过这些材料泵送以使它们变得紧密地处理细颗粒材料 封装。 该方法特别适用于在核工业中遇到的废料，特别是废料的处理。

    Reduction of leachability and solubility of radionuclides and radioactive substances in contaminated soils and materials
    25.
    发明申请
    Reduction of leachability and solubility of radionuclides and radioactive substances in contaminated soils and materials 失效
    降低放射性核素和放射性物质在污染土壤和材料中的浸出性和溶解度

    公开(公告)号：US20020111525A1

    公开(公告)日：2002-08-15

    申请号：US09902533

    申请日：2001-07-09

    Inventor： Dhiraj Pal ,  Karl W. Yost ,  Steven A. Chisick

    IPC: C22B060/02

    CPC classification number: G21F9/304 ,  B09B3/0041 ,  B09C1/08 ,  C02F11/008 ,  C02F2101/006 ,  C02F2101/20 ,  C04B28/34 ,  C04B28/342 ,  C04B28/344 ,  C04B28/346 ,  C04B2111/00767 ,  G21F9/302 ,  Y02W30/91 ,  C04B14/041 ,  C04B18/0472

    Abstract: A process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials, sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB)5(XO4)3Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a suspension containing a sulfate, hydroxide, chloride, fluoride and/or silicate source and a phosphate anion. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

    Abstract translation: 化学固定在土壤，固体物质，污泥和液体中的放射性核素和放射性化合物的过程。 放射性核素和其他放射性化合物通过接触被转化为低温磷灰石组结构同晶（通常组成：（AB）5（XO4）3Z），通常是磷酸盐，其是不溶的，不可浸出的，非沸石的和pH稳定的 含有硫酸盐，氢氧化物，氯化物，氟化物和/或硅酸盐源和磷酸盐阴离子的悬浮液。 磷灰石结构最终产品从初始材料化学改变，体积和质量减小。 最终产品可以没有游离液体，并且表现出足够高的热稳定性水平，以便在发生热反应的情况下有效。 该过程发生在环境温度和压力下。

    Fixation and stabilization of metals in contaminated soils and materials
    27.
    发明授权
    Fixation and stabilization of metals in contaminated soils and materials 失效
    污染土壤和材料中金属的固定和稳定

    公开(公告)号：US5916123A

    公开(公告)日：1999-06-29

    申请号：US942803

    申请日：1997-10-02

    Applicant: Dhiraj Pal ,  Karl W. Yost

    Inventor： Dhiraj Pal ,  Karl W. Yost

    IPC: A62D3/00 ,  A62D3/33 ,  A62D101/24 ,  A62D101/43 ,  B09B3/00 ,  B09C1/08 ,  C02F11/00 ,  C04B28/34 ,  G21F9/30 ,  E02D3/00 ,  G21F9/00

    CPC classification number: G21F9/304 ,  A62D3/33 ,  B09B3/0041 ,  B09C1/08 ,  C02F11/008 ,  C04B18/0472 ,  C04B28/04 ,  C04B28/10 ,  C04B28/14 ,  C04B28/34 ,  G21F9/302 ,  A62D2101/24 ,  A62D2101/43 ,  C02F2101/006 ,  C02F2101/20 ,  C04B2111/00767 ,  Y02W30/58 ,  Y02W30/91

    Abstract: The present invention discloses a method of treating lead bearing process materials and lead toxic hazardous wastes. The invention relates to treatment methods employed to chemically convert leachable lead in lead bearing solid and liquid waste materials to a non-leachable form by mixing the material with lime, gypsum and/or phosphoric acid. The solid and liquid waste materials include contaminated sludges, slurries, soils, wastewaters, spent carbon, sand, wire chips, plastic fluff, cracked battery casings, bird and buck shots and tetraethyl lead contaminated organic peat and muck. The present invention discloses a process comprising a single step mixing of one or more treatment additives, and a process comprising a two step mixing wherein the sequence of performing the steps may be reversible. The present invention provides a new way of treating a universe of lead contaminated materials at any pH.

    Abstract translation: 本发明公开了一种处理含铅工艺材料和铅有毒危险废物的方法。 本发明涉及用于通过将材料与石灰，石膏和/或磷酸混合来将含铅固体和液体废料中的可浸出铅化学转化为不可浸出形式的处理方法。 固体和液体废物包括污染的污泥，泥浆，土壤，废水，废碳，砂，线屑，塑料绒毛，破裂的电池外壳，鸟和屁股和四乙基铅污染的有机泥炭和泥渣。 本发明公开了一种包括一个或多个处理添加剂的单步混合的方法和包括两步混合的方法，其中执行步骤的顺序可以是可逆的。 本发明提供了在任何pH下处理铅污染物质的全新方法。

    Process for the conditioning of radioactive waste using phosphosilicated apatites as the confinement matrix
    29.
    发明授权
    Process for the conditioning of radioactive waste using phosphosilicated apatites as the confinement matrix 失效
    使用磷磷脂磷灰石作为约束基质来调节放射性废物的过程

    公开(公告)号：US5771472A

    公开(公告)日：1998-06-23

    申请号：US591169

    申请日：1995-11-16

    Applicant: Joelle Carpena ,  Jean-Louis Lacout

    Inventor： Joelle Carpena ,  Jean-Louis Lacout

    IPC: B09B3/00 ,  C01B25/16 ,  C01B25/32 ,  C01B33/20 ,  G21F9/30 ,  G21F9/34 ,  G21F9/36 ,  G21F9/00

    CPC classification number: G21F9/304 ,  C01B25/16 ,  C01B33/20 ,  G21F9/34

    Abstract: The invention relates to a process for the conditioning of radioactive waste using silicated apatites as the confinement matrix. This process consists of incorporating the waste (1) into a phosphosilicated apatite-based confinement matrix (3) e.g. complying with the formula: M.sub.t Ca.sub.x Ln.sub.y A.sub.z (PO.sub.4).sub.u (SiO.sub.4).sub.6-u X (I) in which M is an alkali metal, Ln a rare earth, A an actinide, X is S.sup.2-, 2F.sup.-, 2Cl.sup.-, 2Br.sup.-, 2I.sup.- or 2OH.sup.- and u is between 0 and 6.

    Abstract translation: PCT No.PCT / US94 / 00873 Sec。 371日期：1995年11月16日 102（e）日期1995年11月16日PCT 1994年7月12日PCT公布。 公开号WO95 / 02886 日期1995年1月26日本发明涉及使用硅化磷灰石作为约束基质来调节放射性废物的方法。 该方法包括将废物（1）并入磷磷化磷酸盐基封闭基质（3）中，例如 符合以下公式：其中M是碱金属的MtCaxLnyAz（PO4）u（SiO4）6-uX（I），Ln是稀土，A是锕系元素，X是S2-，2F-，2Cl-，2Br-， 2I-或2OH-，u在0和6之间。

    Method for solidifying radioactive waste
    30.
    发明授权
    Method for solidifying radioactive waste 失效
    固化放射性废物的方法

    公开(公告)号：US5481061A

    公开(公告)日：1996-01-02

    申请号：US141541

    申请日：1993-10-27

    Applicant: Kiyomi Funabashi ,  Koichi Chino ,  Osamu Kuriyama ,  Tsutomu Baba ,  Shunsuke Uchida ,  Makoto Kikuchi

    Inventor： Kiyomi Funabashi ,  Koichi Chino ,  Osamu Kuriyama ,  Tsutomu Baba ,  Shunsuke Uchida ,  Makoto Kikuchi

    IPC: C04B28/02 ,  G21F9/16 ,  G21F9/30 ,  G21F9/00

    CPC classification number: C04B28/02 ,  G21F9/16 ,  G21F9/165 ,  G21F9/304

    Abstract: The present invention relates to a method of solidifying radioactive waste with cement, comprising forming a mixture comprising water, a hydrophilic material and cement substantially non-shrinkable or expansible with respect to volume change upon hardening, mixing said mixture with the radioactive waste, followed by hardening to form a solid body.The present invention enables the formation of a compact solid body having voids, such as capillary voids, of reduced volume, which makes it possible to reduce the leaching rate of hazardous materials. Further, since no shrinkage accompanies hardening, no tensile stress occurs in the cement surrounding minute waste particles within the hardened material, thereby enabling a decrease in the strength of the solid body to be minimized. This in turn enables an increase in the amount of packing of waste. Prior addition of a hydrophilic material enables the cement fluidity before hardening to be maintained even after complete absorption of water by a water absorptive waste. This is extremely advantageous in carrying out hardening.

    Abstract translation: 本发明涉及一种用水泥固化放射性废物的方法，包括形成水，亲水材料和水泥在混合物硬化后基本上不可收缩或可膨胀的混合物，将所述混合物与放射性废物混合，然后 硬化形成固体。 本发明能够形成具有减小体积的诸如毛细管空隙的空隙的紧凑的固体，这使得可以降低有害材料的浸出率。 此外，由于没有收缩伴随硬化，所以在硬化材料内的微小废弃颗粒周围的水泥中不产生拉伸应力，从而能够使固体的强度降低到最小。 这又可以增加废物的包装量。 亲水性材料的先前添加使得即使在通过吸水性废物完全吸收水之后，硬化前的水泥流动性仍能保持。 这在进行硬化方面是非常有利的。

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