SILICON CARBIDE MULTILAYERED CLADDING AND NUCLEAR REACTOR FUEL ELEMENT FOR USE IN WATER-COOLED NUCLEAR POWER REACTORS
    2.
    发明申请
    SILICON CARBIDE MULTILAYERED CLADDING AND NUCLEAR REACTOR FUEL ELEMENT FOR USE IN WATER-COOLED NUCLEAR POWER REACTORS 审中-公开
    用于水冷核反应堆的硅碳化物多层粘合剂和核反应堆燃料元件

    公开(公告)号:US20160049211A1

    公开(公告)日:2016-02-18

    申请号:US14012242

    申请日:2013-08-28

    Abstract: A nuclear fuel element for use in water-cooled nuclear power reactors and an improved multilayered silicon carbide tube for use in water-cooled nuclear power reactors and other high temperature, high strength thermal tubing applications including solar energy collectors. The fuel element includes a multilayered silicon carbide cladding tube. The multilayered silicon carbide cladding tube includes (i) an inner layer; (ii) a central layer; and (iii) a crack propagation prevention layer between the inner layer and the central layer. A stack of individual fissionable fuel pellets may be located within the cladding tube. In addition, a thermally conductive layer may be deposited within the cladding tube between the inner layer of the cladding tube and the stack of fuel pellets. The multilayered silicon carbide cladding tube may also be adapted for other high temperature, high strength thermal tubing applications including solar energy collectors.

    Abstract translation: 用于水冷核反应堆的核燃料元件和用于水冷核反应堆和其他高温,高强度热管应用的改进的多层碳化硅管,包括太阳能收集器。 燃料元件包括多层碳化硅包层管。 多层碳化硅包层管包括(i)内层; (ii)中心层; 和(iii)内层和中心层之间的裂纹扩展防止层。 单个可裂变燃料颗粒的堆叠可以位于包层管内。 此外,导热层可以在包壳管内部包覆管的内层和燃料粒料堆之间沉积。 多层碳化硅包覆管也可适用于其它高温,高强度的热管应用,包括太阳能收集器。

    Granulation of Fine Powder
    3.
    发明申请
    Granulation of Fine Powder 有权
    造粒细粉

    公开(公告)号:US20150054184A1

    公开(公告)日:2015-02-26

    申请号:US13971157

    申请日:2013-08-20

    Inventor: Ching-Fong Chen

    Abstract: A mixture of fine powder including thorium oxide was converted to granulated powder by forming a first-green-body and heat treating the first-green-body at a high temperature to strengthen the first-green-body followed by granulation by crushing or milling the heat-treated first-green-body. The granulated powder was achieved by screening through a combination of sieves to achieve the desired granule size distribution. The granulated powder relies on the thermal bonding to maintain its shape and structure. The granulated powder contains no organic binder and can be stored in a radioactive or other extreme environment. The granulated powder was pressed and sintered to form a dense compact with a higher density and more uniform pore size distribution.

    Abstract translation: 将包括氧化钍在内的细粉末的混合物通过形成第一生体并在高温下热处理第一生体而将其转化成粒状粉末,以加强第一生体,然后通过粉碎或研磨制粒 热处理的第一生体。 颗粒粉末通过筛选组合来实现,以获得所需的颗粒尺寸分布。 造粒粉末依赖于热粘合以保持其形状和结构。 造粒粉末不含有机粘合剂,可放置在放射性或其他极端环境中。 将造粒粉末压制并烧结以形成具有更高密度和更均匀孔径分布的致密成型体。

    Binder system for the manufacture of nuclear pellets, and the method and
product thereof
    5.
    发明授权
    Binder system for the manufacture of nuclear pellets, and the method and product thereof 失效
    用于制造核粒料的粘合剂体系及其方法和产品

    公开(公告)号:US4816187A

    公开(公告)日:1989-03-28

    申请号:US22032

    申请日:1987-03-05

    CPC classification number: C04B35/51 G21C3/623 Y02E30/38

    Abstract: A fugitive binder composition for compression molding uranium dioxide nuclear fuel comprising the reaction product of a strongly alkali water solution of a diamine and oxalate ions with uranium oxide which is free of carbonates and carbamates, and having the formula:[.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ][UO.sub.2 (C.sub.2 O.sub.4).sub.2 (H.sub.2 O).sub.2 ][.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ].

    Abstract translation: 一种用于压缩二氧化铀核燃料的短暂的粘结剂组合物,其包含二胺和草酸根离子的强碱性水溶液与不含碳酸盐和氨基甲酸酯的氧化铀的反应产物,并具有下式:[+ NH 3(CH 2)2 NH 3 + ] [&upbar&UO2(C2O4)2(H2O)2] [+ NH3(CH2)2NH3 +]。

    Method for producing nuclear fuel pellets, and product thereof
    6.
    发明授权
    Method for producing nuclear fuel pellets, and product thereof 失效
    生产核燃料颗粒的方法及其制品

    公开(公告)号:US4432915A

    公开(公告)日:1984-02-21

    申请号:US360630

    申请日:1982-03-22

    CPC classification number: G21C3/623 C04B35/51 Y02E30/38

    Abstract: A method for improving the physical properties of pressed bodies or pellets formed of particulate nuclear fuel material containing uranium dioxide. The green or unfired pressed bodies comprise a fugitive binder dispersed through the particulate fuel material.

    Abstract translation: 一种用于改善由含有二氧化铀的颗粒状核燃料材料形成的压制体或丸粒的物理性质的方法。 绿色或未烧制的压制体包括分散在颗粒状燃料材料中的短效粘合剂。

    Process for the production of U.sub.3 O.sub.8 sintered bodies
    8.
    发明授权
    Process for the production of U.sub.3 O.sub.8 sintered bodies 失效
    生产U3O8烧结体的工艺

    公开(公告)号:US4426338A

    公开(公告)日:1984-01-17

    申请号:US274793

    申请日:1981-06-18

    CPC classification number: C04B35/51 G21C3/623 Y02E30/38

    Abstract: For the production of plate shaped fuel elements for material testing and research reactors with highly enriched uranium recently there has been needed U.sub.3 O.sub.8 fuels which have a high density, high strength and a small open porosity. Such fuels are obtained if U.sub.3 O.sub.8 powder produced in known manner is first compressed mechanically to molded bodies of any shape, then processed to a granulate having a size of fuel grains below 200.mu. and subsequently sintered to high density particles, preferably at 1370.degree..+-.50.degree. C.

    Abstract translation: 最近生产用于具有高浓缩铀的材料试验和研究堆的板状燃料元件需要具有高密度,高强度和小开孔度的U3O8燃料。 以已知方式制备的U3O8粉末首先被机械压制成任何形状的成型体,然后加工成具有低于200μm的燃料颗粒尺寸的颗粒并随后烧结成高密度颗粒,优选1370℃/ -50℃

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