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90 条记录 (耗时 0.013 秒)

    Apparatus for locating defective nuclear fuel elements
    82.
    发明授权
    Apparatus for locating defective nuclear fuel elements 失效
    用于定位有缺陷的核燃料元件的设备

    公开(公告)号：US4174255A

    公开(公告)日：1979-11-13

    申请号：US794508

    申请日：1977-05-06

    申请人： William E. Lawrie

    发明人： William E. Lawrie

    IPC分类号： G01N29/22 ,  G01N29/24 ,  G21C17/07 ,  G21C17/00

    CPC分类号： G01N29/245 ,  G01N29/223 ,  G21C17/07

    摘要： An ultrasonic search unit for locating defective fuel elements within a fuel assembly used in a water cooled nuclear reactor is presented. The unit is capable of freely traversing the restricted spaces between the fuel elements.

    摘要翻译： 提出了一种用于在水冷核反应堆中使用的燃料组件内定位有缺陷的燃料元件的超声波搜索单元。 该单元能够自由地穿过燃料元件之间的限制空间。

    Nuclear fuel element leak detection system
    83.
    发明授权
    Nuclear fuel element leak detection system 失效
    核燃料元件泄漏检测系统

    公开(公告)号：US4117333A

    公开(公告)日：1978-09-26

    申请号：US792288

    申请日：1977-04-29

    申请人： Clarence D. John, Jr.

    发明人： Clarence D. John, Jr.

    IPC分类号： G01T1/00 ,  G01M3/20 ,  G21C17/06 ,  G21C17/07 ,  G21C21/00 ,  G01T1/185 ,  G01M3/04 ,  G01T3/00

    CPC分类号： G21C17/07

    摘要： A leak detection system integral with a wall of a building used to fabricate nuclear fuel elements for detecting radiation leakage from the nuclear fuel elements as the fuel elements exit the building. The leak detecting system comprises a shielded compartment constructed to withstand environmental hazards extending into a similarly constructed building and having sealed doors on both ends along with leak detecting apparatus connected to the compartment. The leak detecting system provides a system for removing a nuclear fuel element from its fabrication building while testing for radiation leaks in the fuel element.

    Method and apparatus for the zone-wise shuffling of nuclear reactor fuel elements
    84.
    发明授权
    Method and apparatus for the zone-wise shuffling of nuclear reactor fuel elements 失效
    用于核反应堆燃料元件的区域改组的方法和装置

    公开(公告)号：US4072559A

    公开(公告)日：1978-02-07

    申请号：US635379

    申请日：1975-11-25

    申请人： Herbert Neidl ,  Gunther Kaspar ,  Rolf Drossel

    发明人： Herbert Neidl ,  Gunther Kaspar ,  Rolf Drossel

    IPC分类号： G21C19/02 ,  G21C17/07 ,  G21C19/20 ,  G21C17/06

    CPC分类号： G21C19/205 ,  G21C17/07

    摘要： For zone-wise shuffling of the fuel elements of a nuclear reactor core, single ones of the elements, one after another, are removed sequentially, and immediately upon the removal of each element it is tested for cladding defects, and if free therefrom, immediately inserted back in its new position in the reactor core, elements having cladding defects being eliminated. An apparatus for the rapid testing of each removed element is provided by a testing chamber containing water in which the removed element is immersed and allowed to remain for a short time, the water then being removed and tested for gamma activity to determine the element's cladding integrity. Other features are disclosed.

    摘要翻译： 对于核反应堆核心的燃料元件的区域改组，单个单元之一依次被去除，并且在每个元件移除之后立即进行包覆缺陷的测试，如果不存在，则立即 插入反应堆芯的新位置，消除了具有包层缺陷的元件。 每个去除的元件的快速测试的装置由包含水的测试室提供，其中移除的元件被浸入并允许其保持短时间，然后水被除去并测试γ活性以确定元件的包层完整性 。 公开了其他特征。

    Detection of fuel rod leakage
    85.
    发明授权
    Detection of fuel rod leakage 失效
    检测燃油棒泄漏

    公开(公告)号：US3969187A

    公开(公告)日：1976-07-13

    申请号：US422383

    申请日：1973-12-06

    申请人： Dan L. Worlton, deceased ,  Dan L. Robinson

    发明人： Dan L. Worlton, deceased ,  Dan L. Robinson

    IPC分类号： G01L9/00 ,  G01M3/24 ,  G21C3/16 ,  G21C17/07 ,  G21C17/10

    CPC分类号： G21C17/07 ,  G01L9/0008 ,  G01M3/24 ,  G21C17/102 ,  G21C3/16 ,  Y02E30/40

    摘要： Nuclear reactor fuel rod leakage is determined by measurement of vibrational characteristics of a resilient, flexible means sealed within the upper end caps of the fuel elements. The flexible means, which is preferably a metallic diaphragm, is set into motion by the impact of an internal metal rod which is operated by an external magnetic field, thereby permitting an indication of the pressure inside a fuel element without disturbing the welded assembly. The metal rod is activated and the vibration measurements are made through the use of a special tool which fits near the end cap of the fuel element to be tested.

    摘要翻译： 核反应堆燃料棒泄漏通过测量密封在燃料元件的上端盖内的弹性的柔性装置的振动特性来确定。 优选地是金属隔膜的柔性装置通过由外部磁场操作的内部金属杆的冲击而被设置成运动，从而允许指示燃料元件内部的压力而不干扰焊接组件。 金属杆被激活，并且通过使用适合待测试的燃料元件的端盖附近的专用工具来进行振动测量。