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    • 2. 发明专利
    • Fuel supporting fixture
    • 燃油支撑件
    • JP2005049132A
    • 2005-02-24
    • JP2003203954
    • 2003-07-30
    • Toshiba Corp株式会社東芝
    • SHIRAKAWA TAKEETSUKATO TATSUMAMOROOKA SHINICHIAKIBA YOSHIYUKIYAMAMOTO YASUSHI
    • G21C5/06G21C15/02
    • Y02E30/31
    • PROBLEM TO BE SOLVED: To prevent the misinstallation on directions, positions and the like when a foreign body capturing filter is mounted on a coolant inflow mouth of a fuel supporting fixture.
      SOLUTION: In the fuel supporting fixture 7 which supports the lower part of nuclear fuel assemblies and includes a coolant flow channel chamber that guides a coolant from the coolant inflow mouth 16 toward the nuclear fuel assemblies, a filter plate 50 which has a filter part 32 and a filter frame 30 surrounding it is fitted onto the coolant inflow mouth 16 from outside it. The filter part 32 has a property which varies with the relative flow directions of the coolant. A recess 31 for accepting and holding the periphery of the filter plate 50 is formed in the coolant inflow mouth 16. The configurations of the periphery of the filter plate 50 and the recess 31 are so asymmetric that they can fit onto each other. The filter plate 50 is so constituted that the direction of it can be limited by the recess 31 when the filter plate 50 is fitted.
      COPYRIGHT: (C)2005,JPO&NCIPI
    • 要解决的问题:为了防止在异物捕获过滤器安装在燃料支撑夹具的冷却剂流入口上时的方向,位置等上的错误安装。 解决方案:在支撑核燃料组件的下部并且包括将冷却剂从冷却剂流入口16引向核燃料组件的冷却剂流动通道室的燃料支撑固定件7中,过滤板50具有 过滤器部分32和围绕它的过滤器框架30从外部装配到冷却剂流入口16上。 过滤器部件32具有随冷却剂的相对流动方向而变化的特性。 在冷却剂流入口16中形成有用于接收和保持过滤板50的周边的凹部31.过滤板50和凹部31的周边的构造非常不对称,使得它们彼此配合。 过滤板50的构造使得当安装过滤板50时,其方向可以被凹部31限制。 版权所有(C)2005,JPO&NCIPI
    • 8. 发明专利
    • Simulated fuel rod for nuclear reactor
    • 用于核反应堆的模拟燃料油
    • JP2008064548A
    • 2008-03-21
    • JP2006241578
    • 2006-09-06
    • Toshiba Corp株式会社東芝
    • AKIBA YOSHIYUKIMOROOKA SHINICHI
    • G21C17/00
    • PROBLEM TO BE SOLVED: To provide a simulated fuel rod for a nuclear reactor enabling an evaluation test of accurate heat transfer flow performance by further approximating the surface state of a cladding tube to the surface state of a real nuclear fuel rod.
      SOLUTION: The simulated fuel rod for a nuclear reactor, simulating the surface state of a real nuclear fuel rod of a nuclear reactor, is used for executing an evaluation test of the heat transfer flow performance of a nuclear fuel rod and comprises a cladding tube 2, a heater 4 and an electric insulator 3 housed in the cladding tube 2, and a thermocouple 5 embedded in a fitting groove 10 formed in the outer surface of the cladding tube 2. A metallic flame-sprayed layer 11 is formed on the surface of the cladding tube 4.
      COPYRIGHT: (C)2008,JPO&INPIT
    • 要解决的问题:提供一种用于核反应堆的模拟燃料棒,其能够通过进一步将包壳管的表面状态近似到真实核燃料棒的表面状态来进行准确的传热流动性能的评估测试。 解决方案:用于模拟核反应堆的真实核燃料棒的表面状态的用于核反应堆的模拟燃料棒用于执行核燃料棒的传热流性能的评估试验,并且包括 包层管2,加热器4和容纳在包层管2中的电绝缘体3,以及嵌入在包层管2的外表面上的嵌合槽10中的热电偶5.金属火焰喷涂层11形成在 包层管4的表面。版权所有(C)2008,JPO&INPIT