FIBREGLASS BIN AND WASTE INCINERATION METHOD
    81.
    发明申请
    FIBREGLASS BIN AND WASTE INCINERATION METHOD 有权
    FIBERGLASS BIN和WASTE INCINERATION方法

    公开(公告)号:US20150369480A1

    公开(公告)日:2015-12-24

    申请号:US14766290

    申请日:2014-02-13

    申请人: AREVA NC

    摘要: The basket according to the invention can be used to incinerate waste inside an incinerator for a duration longer than fifteen minutes with no need for waste to be molten earlier, particularly when waste is introduced inside the incinerator. The basket is composed mainly of a glass fibre envelope (10): it is preferably stiffened by a lightweight metal structure (12) located inside or outside the envelope or built into it. A gripping handle (14) is installed on top of the assembly that is stiffened at the top by a metal tube (16) to which a lightweight metal structure (12) is fixed and by a base formed from a drip pan (18) fixed to the base of the lightweight metal structure (12). Application for incineration of toxic waste.

    摘要翻译: 根据本发明的篮子可用于将焚化炉内的废物焚化长达十五分钟以上,而不需要较早地将废物熔化,特别是当废物被引入焚化炉内时。 篮子主要由玻璃纤维外壳(10)组成:优选地由位于信封内部或外部的轻质金属结构(12)加固,或者内置于其中。 夹紧手柄(14)安装在组件的顶部,该顶部由金属管(16)加固,轻金属结构(12)固定在该金属管(16)上,并由固定的滴水盘(18)形成的底座 到轻质金属结构(12)的基部。 焚化有毒废物的申请。

    MULTIFUNCTIONAL CHAMBERED RADIATION SHIELDS AND SYSTEMS AND RELATED METHODS
    84.
    发明申请
    MULTIFUNCTIONAL CHAMBERED RADIATION SHIELDS AND SYSTEMS AND RELATED METHODS 有权
    多功能散热片和系统及相关方法

    公开(公告)号:US20120273622A1

    公开(公告)日:2012-11-01

    申请号:US13095659

    申请日:2011-04-27

    申请人: David S. Long

    发明人: David S. Long

    IPC分类号: B64G1/54 B23P11/00 G21F3/00

    摘要: Radiation shields include an outer composite wall, an inner composite wall, and an enclosed fuel chamber disposed between the inner and outer composite walls. A fuel may be contained within the enclosed fuel chamber. Spacecraft include one or more such radiation shields, and may further include a fuel cell and a conduit providing fluid communication between the fuel chamber of the radiation shield and the fuel cell. Methods of forming a radiation shield system include forming an enclosed fuel chamber between an outer composite wall and an inner composite wall of a radiation shield, and providing fuel within the enclosed fuel chamber.

    摘要翻译: 辐射屏蔽包括外复合壁,内复合壁和设置在内外复合壁之间的封闭燃料室。 燃料可以被包含在封闭的燃料室内。 航天器包括一个或多个这样的辐射屏蔽,并且还可以包括燃料电池和提供辐射屏蔽的燃料室与燃料电池之间的流体连通的导管。 形成辐射屏蔽系统的方法包括在外部复合壁和辐射屏蔽的内部复合壁之间形成封闭的燃料室,并在封闭的燃料室内提供燃料。

    Composite materials and techniques for neutron and gamma radiation shielding
    86.
    发明授权
    Composite materials and techniques for neutron and gamma radiation shielding 有权
    用于中子和γ射线屏蔽的复合材料和技术

    公开(公告)号:US07250119B2

    公开(公告)日:2007-07-31

    申请号:US11121852

    申请日:2005-05-04

    摘要: This invention deals with multi-component composite materials and techniques for improved shielding of neutron and gamma radiation emitting from transuranic, high-level and low-level radioactive wastes. Selective naturally occurring mineral materials are utilized to formulate, in various proportions, multi-component composite materials. Such materials are enriched with atoms that provide a substantial cumulative absorptive capacity to absorb or shield neutron and gamma radiation of variable fluxes and energies. The use of naturally occurring minerals in synergistic combination with formulated modified cement grout matrix, polymer modified asphaltene and maltene grout matrix, and polymer modified polyurethane foam grout matrix provide the radiation shielding product. These grout matrices are used as carriers for the radiation shielding composite materials and offer desired engineering and thermal attributes for various radiation management applications.

    摘要翻译: 本发明涉及用于改善从超铀,高水平和低放射性废物排放的中子和γ辐射屏蔽的多组分复合材料和技术。 选择性天然存在的矿物材料用于以多种比例配制多组分复合材料。 这些材料富含原子,这些原子提供了大量的累积吸收能力来吸收或屏蔽可变通量和能量的中子和γ辐射。 使用天然存在的矿物质与配制的改性水泥浆料基质,聚合物改性沥青质和麦芽浆浆料基质以及聚合物改性聚氨酯泡沫浆料基质协同组合提供辐射屏蔽产品。 这些灌浆基质用作辐射屏蔽复合材料的载体,并为各种辐射管理应用提供所需的工程和热属性。

    Radiation shielding glass and radiation shielding article using the same
    87.
    发明申请
    Radiation shielding glass and radiation shielding article using the same 审中-公开
    辐射屏蔽玻璃和使用其的辐射屏蔽物品

    公开(公告)号:US20050221973A1

    公开(公告)日:2005-10-06

    申请号:US10512226

    申请日:2003-04-18

    摘要: A radiation shielding article 10 is in the form of a plurality of radiation shielding glasses 11 that are stuck together with resin films 12 therebetween, respectively. Each radiation shielding glass 11 is made of glass essentially free of Pb and having a lead equivalent of 0.03 mmPb/mm or more relative to an X-ray of 100 kV. Further, each radiation shielding glass 11 has a composition containing, by mass %, 50 to 65% of SO2, 5 to 15% of Al2O3, 0.1 to 9% of ZrO2, 10 to 27% of MgO+CaO+SrO+BaO+ZnO, and 7 to 15% of Li2O+Na2O+K2O.

    摘要翻译: 辐射屏蔽制品10是多个辐射屏蔽眼镜11的形式,它们分别与它们之间的树脂膜12粘合在一起。 每个辐射屏蔽玻璃11由基本上不含Pb并且相对于100kV的X射线的相当于0.03mmPb / mm以上的铅的玻璃制成。 此外,每个辐射屏蔽玻璃11具有以质量%计含有50〜65%的SO 2,5〜15%的Al 2 O 3 0.1〜9%的ZrO 2,10〜27%的MgO + CaO + SrO + BaO + ZnO,7〜15%的Li 2 O 3, O + Na 2 O + K 2 O。

    Porcelain enamel neutron absorbing material
    88.
    依法登记的发明
    Porcelain enamel neutron absorbing material 失效
    瓷搪瓷中子吸收材料

    公开(公告)号:USH744H

    公开(公告)日:1990-02-06

    申请号:US123462

    申请日:1987-11-20

    申请人: Daniel C. Iverson

    发明人: Daniel C. Iverson

    摘要: A porcelain enamel composition as a neutron absorbing material can be prepared of a major proportion by weight of a cadmium compound and a minor proportion of compounds of boron, lithium and silicon. These compounds in the form of a porcelain enamel coating or layer on several alloys has been found to be particularly effective in enhancing the nuclear safety of equipment for use in the processing and storage of fissile material. The composition of the porcelain enamel coating can be tailored to match the coefficient of thermal expansion of the equipment to be coated and excellent coating adhesion can be achieved.

    Ceramic bonded neutron absorber plates of boron carbide and free carbon
    89.
    发明授权
    Ceramic bonded neutron absorber plates of boron carbide and free carbon 失效
    陶瓷粘结中子吸收板碳化硼和游离碳

    公开(公告)号:US4684480A

    公开(公告)日:1987-08-04

    申请号:US670760

    申请日:1984-11-13

    摘要: The invention is a ceramically-bonded large-area neutron absorber articles of low density having a space filling ofabout 40 to 60% by volume boron carbide+silicon carbide in a B.sub.4 C:SiC ratio of about 9:1 to 1:9 andabout 10 to 20% by volume of free carbon, the remainder pores.They have a density of from about 1.5 to 2.2 g/cm.sup.3 and a flexural strength of from about 20 to 50 N/mm.sup.2 at room temperature measured according to the 3-point method, which strength after the corrosion test of immersion for about 3000 hours in boiling water, drops by less than about 40% of the initial value. Graphite powder may optionally be included with a pulverulent organic resin binder and a wetting agent, molding the mixture under pressure at about room temperature, curing the resin binder at temperatures of up to about 180.degree. C. and then coking the molded plates in the absence of air at temperatures of up to about 1000.degree. C. under a controlled temperature program.

    摘要翻译: 本发明是一种低密度陶瓷结合的大面积中子吸收体制品,具有约40至60体积%的碳化硼+碳化硅的空间填充体,其中B4C:SiC比为约9:1至1:9,约为 10〜20体积%的游离碳,其余为毛孔。 它们的密度约为1.5-2.2g / cm3,室温下的弯曲强度为约20至50N / mm 2,根据3点法测定,浸渍腐蚀试验后的强度约为3000小时 在沸水中下降小于初始值的约40%。 可以任选地在粉状有机树脂粘合剂和润湿剂中包含石墨粉末,在约室温下在压力下成型混合物,在高达约180℃的温度下固化树脂粘合剂,然后在不存在的情况下将模制板焦化 的空气在高达约1000℃的温度下控制温度程序。