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    • 9. 发明公开
    • LIGHT-WATER-REACTOR FUEL ROD, AND FUEL ASSEMBLY
    • 轻水反应堆燃料杆和燃料组件
    • EP3239985A1
    • 2017-11-01
    • EP15902245.8
    • 2015-08-25
    • Hitachi, Ltd.
    • ISHIBASHI, RyouTAKAMORI, YoshiyukiZHANG, Xudong
    • G21C3/06G21C3/10G21C3/30G21C21/02
    • G21C3/10G21C3/06G21C3/07G21C3/30G21C21/02G21Y2002/102G21Y2002/207Y02E30/40
    • Provided herein is a fuel rod and a fuel assembly for light water reactors in which crack penetration to a fuel cladding tube or an end plug can be prevented even when cracking occurs at the joint between the fuel cladding tube and the end plug for which a ceramic base material is used. A fuel rod 10a for light water reactors includes: a cylindrical cladding tube 11 formed of a ceramic base material; a connection 21 formed of the same or similar material to the cladding tube 11; and an end plug 12a having a concave portion 12f of a continuously curved surface shape adapted to house the connection 21. The end plug 12a is formed of the same or similar material to the cladding tube 11. A slanted surface 11a formed at an end portion of the cladding tube 11, and a slanted surface 12d formed at an end portion of the end plug 12a are joined in contact with each other with a metallic joint material 20. The joint is supported by the connection 21.
    • 本文提供了一种用于轻水反应堆的燃料棒和燃料组件,其中即使在燃料包壳管和陶瓷端塞的接合处发生裂纹时,也可防止裂纹渗入燃料包壳管或端塞, 使用基材。 用于轻水反应堆的燃料棒10a包括:由陶瓷基材形成的圆筒形包层管11; 由与包壳管11相同或相似的材料形成的连接部21; 以及具有适于容纳连接件21的连续曲面形状的凹部12f的端塞12a。端塞12a由与包层管11相同或类似的材料形成。倾斜表面11a形成在端部 以及形成在端塞12a的端部处的倾斜表面12d利用金属接头材料20彼此接触地接合。接头由连接件21支撑。
    • 10. 发明公开
    • NUCLEAR FUEL PELLET HAVING ENHANCED THERMAL CONDUCTIVITY, AND PREPARATION METHOD THEREOF
    • KERNBRENNSTOFFTABLETTEN MIT VERBESSERTERWÄRMELEITFÄHIGKEITUND HERSTELLUNGSVERFAHRENDAFÜR
    • EP3076398A4
    • 2017-06-21
    • EP14865710
    • 2014-11-21
    • JOINT STOCK COMPANY AKME-ENGINEERING
    • KURINA IRINA SEMYONOVNAPOPOV VJACHESLAV VASILYEVICHRUMYANTSEV VLADIMIR NIKOLAEVICHRUSANOV ALEKSANDER EVGENIEVICHROGOV STEPAN SERGEEVICHSHARIKPULOV SAID MIRFAISOVICH
    • G21C3/04G21C3/58G21C3/62
    • G21C3/623G21C3/044G21C3/58G21C21/02G21C2003/045Y02E30/38
    • The invention relates to nuclear physics, and specifically to reactor fuel elements and units thereof, and particularly to the composition of solid ceramic fuel elements based on uranium dioxide, intended for and exhibiting characteristics for being used in variously purposed nuclear reactors. The result consists in a more reliable, special structure and a simple composition of uranium dioxide without heterogeneous fuel pellet additives, approaching the characteristics of a monocrystal having enhanced, and specifically exceeding reference data, thermal conductivity as temperature increases, and a simple production method thereof. The result is achieved in that pores of between 1 and 5 microns in size are distributed along the perimeters of grains in the micro-structure of each metal cluster in a nuclear fuel pellet, and in that located within the grains are pores which are predominantly nano-sized. In addition, the metal clusters comprise between 0.01 and 1.0 percent by mass. The invention provides for a method of preparing a nuclear fuel pellet, including precipitating metal hydroxides, in two stages, having different pH levels. Uranium metal is melted at a temperature exceeding 1150°C, sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200°C in a hydrogen medium until forming uranium dioxide, the structure of which includes metal clusters dispersed therein. An X-ray photon spectroscope is used for identifying the new structure of the UO2 pellet and the additional U-U chemical bond.
    • 本发明涉及核物理学,具体涉及反应堆燃料元件及其单元,并且具体涉及基于二氧化铀的固体陶瓷燃料元件的组合物,旨在用于并表现出用于各种目的的核反应堆的特征。 其结果是具有更可靠,特殊的结构和二氧化铀的简单组成,没有非均质燃料颗粒添加剂,接近单晶的特性已经提高,特别是超过参考数据,随着温度升高导热率,以及其简单的生产方法 。 其结果得以实现,其尺寸在1至5微米之间的孔隙沿着核燃料芯块中每个金属簇的微观结构中的晶粒的周边分布,并且位于晶粒内的是主要为纳米 尺度的。 另外,金属团簇包含0.01-1.0质量%。 本发明提供了一种制备核燃料芯块的方法,该方法包括两步沉淀金属氢氧化物,具有不同的pH值。 铀金属在超过1150℃的温度下熔化,在氢气介质中在1600和2200℃之间的温度范围内,在不明显量的液相中进行烧结,直至形成二氧化铀,其结构包括分散的金属团簇 在其中。 X射线光子分光镜用于识别UO2颗粒的新结构和额外的U-U化学键。