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    • 6. 发明授权
    • Container for storing radioactive materials
    • 储存放射性物质的集装箱
    • US07335902B2
    • 2008-02-26
    • US10918229
    • 2004-08-13
    • Rengarajan Soundararajan
    • Rengarajan Soundararajan
    • G21F5/00G21F1/00G21F1/10C09K3/00G21C7/24
    • G21F9/36C08G18/2018C08G18/542C08G18/7664C08K3/08C09D175/04F23G5/027F23G7/003F23G2201/301F23G2201/302F23G2209/18G21F1/106G21F9/06G21F9/30G21F9/305G21F9/307C08L75/04
    • A urethane based polymer composition is provided that exhibits superior shielding properties during and after exposure to high level radiation. The composite is formed by mixing a liquid isocyanate monomer, preferably 4,4′-diisocyanate monomer with a liquid phenolic resin, preferably phenol formaldehyde resin, and a phosphate ester flame retardant. An optional pyridine catalyst may be added to shorten the cure time. The resulting composition cures at room temperature and can be utilized in several manners, including spraying or pouring the composition prior to curing over radioactive material to prevent leakage of radiation. The uncured composite can be sprayed on the walls of a room or container to prevent leakage of radiation and can also be used to contain radiation prior to demolition. The uncured composite can also be molded into bricks or panels for use in construction. In a preferred embodiment, the polymer composition further incorporates radioactive waste, namely depleted uranium oxide, and can be used in conjunction with specially designed containers for storing radioactive material. The resulting polymer/waste composition cures at room temperature and does not deteriorate or suffer structural damage when exposed to higher levels of gamma radiation, nor do the mechanical or chemical properties undergo any detectable change. The composition is resistant to biodegradation and combustion, and does not creep or shrink during thermal cycling.
    • 提供了一种聚氨酯基聚合物组合物,其在暴露于高水平辐射期间和之后显示优异的屏蔽性能。 复合材料通过将液体异氰酸酯单体,优选4,4'-二异氰酸酯单体与液体酚醛树脂,优选苯酚甲醛树脂和磷酸酯阻燃剂混合而形成。 可以加入任选的吡啶催化剂以缩短固化时间。 所得组合物在室温下固化并且可以以几种方式使用,包括在固化放射性材料之前喷涂或浇注组合物以防止辐射泄漏。 未固化的复合材料可以喷涂在房间或容器的壁上,以防止辐射泄漏,并且还可以用于在拆除之前容纳辐射。 未固化的复合材料也可以模制成砖或面板用于施工。 在优选的实施方案中,聚合物组合物还包含放射性废物,即贫化铀氧化物,并且可以与用于储存放射性物质的专门设计的容器结合使用。 所得聚合物/废物组合物在室温下固化,并且在暴露于较高水平的γ辐射时不会劣化或遭受结构损伤,机械或化学性质也不会发生任何可检测的变化。 该组合物耐生物降解和燃烧,并且在热循环期间不会蠕变或收缩。
    • 8. 发明授权
    • High neutron absorbing refractory compositions of matter and methods for
their manufacture
    • 高中子吸收耐火材料组合物及其制造方法
    • US5273709A
    • 1993-12-28
    • US933859
    • 1992-08-24
    • Danny C. HalversonGarth W. BillingsGeorge M. Johnston
    • Danny C. HalversonGarth W. BillingsGeorge M. Johnston
    • G21C7/24B22F3/12
    • G21C7/24Y02E30/39
    • Neutron absorbing refractory B.sub.4 C-Gd and Gd.sub.2 O.sub.3 -Gd cermets, B.sub.4 C-Gd and Gd.sub.2 O.sub.3 -Gd metal-matrix composites, and B.sub.4 C-Gd.sub.2 O.sub.3 ceramic-ceramic composites can be manufactured by applying fundamental thermodynamic and kinetic guidelines as processing principals.Three steps are involved in the fabrication of these new compositions of matter. First, the starting materials are consolidated into a compacted porous green body. Next, the green body is densified using the appropriate method depending on the class of material sought: cermet, metal-matrix composite, or ceramic-ceramic composite. Finally, either during the densification process or by subsequent heat treatment, new phase evolution is obtained via interfacial chemical reactions occurring in the microstructures.The existence of a new phase has been identified in B.sub.4 C-Gd and B.sub.4 C-Gd.sub.2 O.sub.3 composites.
    • 中子吸收耐火材料B4C-Gd和Gd2O3-Gd金属陶瓷,B4C-Gd和Gd2O3-Gd金属基复合材料以及B4C-Gd2O3陶瓷陶瓷复合材料可以通过应用基本的热力学和动力学指导作为加工原理来制造。 这些新的物质组合物的制造涉及三个步骤。 首先,起始材料被固结成压实的多孔生坯。 接下来,根据所寻求的材料类别,使用适当的方法使生坯体致密化:金属陶瓷,金属基复合材料或陶瓷 - 陶瓷复合材料。 最后,在致密化过程中或通过随后的热处理,通过在微结构中发生的界面化学反应获得新的相变。 在B4C-Gd和B4C-Gd2O3复合材料中已经发现了新相的存在。