MATERIAL MOISTURE CONTENT ADJUSTMENT METHOD
    91.
    发明申请
    MATERIAL MOISTURE CONTENT ADJUSTMENT METHOD 有权
    材料水分含量调整方法

    公开(公告)号:US20090016149A1

    公开(公告)日:2009-01-15

    申请号:US11909499

    申请日:2006-03-27

    IPC分类号: B01F15/06

    摘要: When making moisture content adjustment by adding liquid such as water to a raw material such as pulverulent material including bentonite, uniform mixing of the liquid such as water with the raw material is given with relatively simple facilities, moisture content adjustment of a large quantity of raw materials is attainable, and besides, a material having satisfactory performances such as impermeability is obtainable through uniform moisture content adjustment. Within a mixing tank (1) configured with a normal powder mixer kept at low temperatures, pulverulent bentonite (A) and fine granular ice (B) are stirred and mixed. Stirring and mixing of the fellow pulverulent materials are adapted to uniformly mix the pulverulent bentonite (A) and the fine granular ice (B), enabling uniformly moisture content-adjusted bentonite to be obtained. A liquid-nitrogen gas bomb (21), for instance, is connected to the mixing tank (1), causing the inside of the mixing tank to be kept at low temperatures with nitrogen gas supplied from the bomb, before putting the prepared fine granular ice (B) through an inlet port (20).

    摘要翻译: 当通过向诸如膨润土的粉末材料等原料添加水等水分进行水分含量调节时,以比较简单的设备使水等液体与原料均匀混合,大量原料 可以获得材料,此外,通过均匀的含水量调节可获得具有令人满意的性能如不渗透性的材料。 在配置有保持在低温下的普通粉末混合器的混合罐(1)中,搅拌混合粉状膨润土(A)和细粒状冰(B)。 搅拌和混合粉末状材料适于均匀混合粉状膨润土(A)和细粒状冰(B),从而可获得均匀的含水量调节膨润土。 例如,将液氮气体炸弹(21)连接到混合罐(1),在将制备好的细颗粒 冰(B)通过入口(20)。

    Encapsulation of waste
    92.
    发明授权
    Encapsulation of waste 失效
    垃圾的封装

    公开(公告)号:US07078581B1

    公开(公告)日:2006-07-18

    申请号:US10129310

    申请日:2000-11-08

    IPC分类号: G21F9/34 G21F9/28 G21F9/20

    CPC分类号: G21F9/162

    摘要: A ceramic waste immobilizing material for the encapsulation of high level radioactive waste (HLW), e.g. resulting from the reprocessing of irradiated nuclear fuel. The ceramic waste immobilising material enables waste ions from at least fission products in irradiated nuclear fuel to be dissolved in substantially solid solution form. The ceramic waste immobilising medium has a matrix comprising phases of hollandite, perovskite and zirconolite in which the waste ions are dissolved. The invention also includes a method of immobilizing HLW from reprocessed nuclear fuel assemblies comprising the steps of mixing a liquor containing the HLW with a precursor material comprising oxides or oxide precursors of at least titanium, calcium and barium to form a slurry, drying the slurry, and calcining the dried slurry under a reducing atmosphere to form a powder comprising 30–65 weight % waste.

    摘要翻译: 用于封装高放射性废物(HLW)的陶瓷废物固定材料,例如, 由辐射核燃料的后处理造成的。 陶瓷废物固定材料使来自辐射核燃料中的至少裂变产物的废物离子以基本上固溶的形式溶解。 陶瓷废物固定介质具有包括其中废离子溶解的地幔,钙钛矿和锆石的相的基体。 本发明还包括一种从再处理的核燃料组件固定HLW的方法,包括以下步骤:将含有HLW的液体与包含至少钛,钙和钡的氧化物或氧化物前体的前体材料混合以形成浆料,干燥浆料, 并在还原气氛下煅烧干燥的浆料以形成包含30-65重量%废物的粉末。

    Processes for immobilizing radioactive and hazardous wastes
    93.
    发明授权
    Processes for immobilizing radioactive and hazardous wastes 失效
    固定放射性和危险废物的过程

    公开(公告)号:US06734334B2

    公开(公告)日:2004-05-11

    申请号:US09810557

    申请日:2001-03-19

    IPC分类号: G21F100

    摘要: The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the waste. Each of the processes create a barrier against leaching and diffusion of the wastes. The first barrier is created by integrating the waste with an immobilizing mineral. The second barrier is a layer of non-radioactive or non-hazardous material that covers the first barrier. The second barrier may be created using an overgrowth procedure or by sintering. The third barrier is created by a rock or glass matrix that surrounds the first and/or second barriers. The fourth barrier is created by ensuring that the rock or glass has the same or similar composition as the indigenous rock at the disposal site. The resultant rock or glass matrix is in equilibrium with the groundwater or local hydrothermal solutions that are saturated with components of the indigenous rock of the disposal area.

    摘要翻译: 本发明利用一种或多种方法固定含有一种或多种放射性核素,危险元素,危险化合物和/或废物中存在的其它化合物的废物。 每个过程都会产生阻碍废物浸出和扩散的障碍。 第一个障碍是通过将废物与固定矿物相结合而形成的。 第二个屏障是覆盖第一个屏障的一层非放射性或非危险材料。 可以使用过度生长程序或通过烧结来产生第二阻挡层。 第三个障碍是围绕第一和/或第二个障碍物的岩石或玻璃基质产生的。 第四个障碍是通过确保岩石或玻璃与处置场所的本土岩石具有相同或相似的组成来创建的。 所得到的岩石或玻璃基质与地下水或当地的热液溶液处于平衡状态,该溶液饱和了处置区的本土岩石的组分。

    Method for conditioning soda effluents in the form of nepheline
    95.
    发明申请
    Method for conditioning soda effluents in the form of nepheline 有权
    以霞石的形式调节苏打水的方法

    公开(公告)号:US20020198431A1

    公开(公告)日:2002-12-26

    申请号:US10149958

    申请日:2002-06-17

    IPC分类号: C01B039/18

    CPC分类号: G21F9/06 G21F9/162

    摘要: This invention relates to a method for conditioning a waste constituted of an aqueous solution of sodium hydroxide NaOH of 3 to 10 M, possibly radioactive. The method is as follows: a) a metakaolin powder is added to the aqueous solution such that a suspension is obtained capable of solidifying and forming a crystalline phase of the zeolite A type; b) the suspension is introduced into a mould; c) the suspension is left to solidify in the mould in order to obtain a moulded solid product based on zeolite A; d) the moulded product is dried; and e) the zeolite A phase is converted into a nepheline type phase by heat treatment at a temperature of 1000null C. to 1500null C.

    摘要翻译: 本发明涉及一种用于调节由可能具有放射性的3至10M的氢氧化钠NaOH水溶液构成的废物的方法。 方法如下:a)向水溶液中加入偏高岭土粉末,得到能够凝固形成沸石A型结晶相的悬浮液; b)将悬浮液引入模具中; c)将悬浮液在模具中固化以获得基于沸石A的模制固体产物; d)将成型品干燥; 和e)通过在1000℃至1500℃的温度下热处理将沸石A相转化成霞石型相。

    Processes for immobilizing radioactive and hazardous wastes
    96.
    发明申请
    Processes for immobilizing radioactive and hazardous wastes 失效
    固定放射性和危险废物的过程

    公开(公告)号:US20020038070A1

    公开(公告)日:2002-03-28

    申请号:US09810557

    申请日:2001-03-19

    IPC分类号: B09B001/00

    摘要: The present invention utilizes one or more processes to immobilize a waste that contains one or more of radionuclides, hazardous elements, hazardous compounds, and/or other compounds present in the waste. Each of the processes create a barrier against leaching and diffusion of the wastes. The first barrier is created by integrating the waste with an immobilizing mineral. The second barrier is a layer of non-radioactive or non-hazardous material that covers the first barrier. The second barrier may be created using an overgrowth procedure or by sintering. The third barrier is created by a rock or glass matrix that surrounds the first and/or second barriers. The fourth barrier is created by ensuring that the rock or glass has the same or similar composition as the indigenous rock at the disposal site. The resultant rock or glass matrix is in equilibrium with the groundwater or local hydrothermal solutions that are saturated with components of the indigenous rock of the disposal area.

    摘要翻译: 本发明利用一种或多种方法固定含有一种或多种放射性核素,危险元素,危险化合物和/或废物中存在的其它化合物的废物。 每个过程都会产生阻碍废物浸出和扩散的障碍。 第一个障碍是通过将废物与固定矿物相结合而形成的。 第二个屏障是覆盖第一个屏障的一层非放射性或非危险材料。 可以使用过度生长程序或通过烧结来产生第二阻挡层。 第三个障碍是围绕第一和/或第二个障碍物的岩石或玻璃基质产生的。 第四个障碍是通过确保岩石或玻璃与处置场所的本土岩石具有相同或相似的组成来创建的。 所得到的岩石或玻璃基质与地下水或局部热液溶液处于平衡状态,该溶液饱和了处置区的本土岩石的组分。

    Process for the preparation of a borosilicate glass containing nuclear
waste
    100.
    发明授权
    Process for the preparation of a borosilicate glass containing nuclear waste 失效
    制备含有核废料的硼硅酸盐玻璃的方法

    公开(公告)号:US4797232A

    公开(公告)日:1989-01-10

    申请号:US35051

    申请日:1987-04-06

    申请人: Bruno Aubert

    发明人: Bruno Aubert

    CPC分类号: G21F9/305 G21F9/162

    摘要: The invention relates to a process for the preparation of a borosilicate glass containing nuclear waste.In this process, an inactive borosilicate matrix is prepared in an aqueous medium by mixing the following:a silica-based gel precursor,a concentrated aqueous solution of a boron compound, anda concentrated aqeuous solution of the vitrification adjuvant,in proportions corresponding to the composition of the final glass minus the waste, with stirring at a high rate of shear, at a temperature of between 20.degree. C. and 80.degree. C., preferably at 65.degree.-70.degree. C., at an acid pH, preferably a pH of between 2.5 and 3.5, so as to form a gelled solution, and the said matrix is heat-treated and the nuclear waste is added at any stage during the said treatment to form, by melting, the final borosilicate glass containing the said waste.The process according to the invention is applied to the treatment of nuclear waste, especially to solutions of fission products.

    摘要翻译: 本发明涉及一种制备含有核废料的硼硅酸盐玻璃的方法。 在该方法中,在水性介质中通过以下方式制备无水硼硅酸盐基质:将二氧化硅基凝胶前体,浓硼酸化水溶液和玻璃化助剂的浓缩溶液混合,其比例对应于 最后的玻璃的组成减去废物,在高剪切速率下搅拌,温度在20℃至80℃之间,优选在65℃-70℃,酸度下,优选为 pH为2.5至3.5,以形成凝胶溶液,并且所述基质被热处理,并且在所述处理期间的任何阶段加入核废料,以通过熔化形成含有所述废物的最终硼硅酸盐玻璃 。 根据本发明的方法用于处理核废料,特别是裂解产物的溶液。