DEVICE AND METHOD FOR PERFORMING A LEAK TEST ON FUEL ROD CAPSULES

    公开(公告)号:US20180010979A1

    公开(公告)日:2018-01-11

    申请号:US15535876

    申请日:2015-12-07

    申请人: AREVA GmbH

    发明人: Wolfgang HUMMEL

    IPC分类号: G01M3/20 G21C17/07 G21C19/07

    CPC分类号: G01M3/205 G21C17/07 G21C19/07

    摘要: The invention relates to a device for performing a leak test on a fuel rod capsule, which contains at least one fuel rod and test gas, which device comprises a test container, which is designed to accommodate at least one fuel rod capsule and can be lowered into a pool of a nuclear plant flooded with water. According to the invention, a mass spectrometer is fluidically connected to the interior of the test container in such a way that a gas flow can be fed to the mass spectrometer in order to sense the concentration of the test gas that has diffused into the test container from the fuel rod capsule.

    SYSTEM AND METHOD FOR IMPROVING SENSITIVITY OF A SIPPING SYSTEM
    33.
    发明申请
    SYSTEM AND METHOD FOR IMPROVING SENSITIVITY OF A SIPPING SYSTEM 审中-公开
    提高SIPPING系统灵敏度的系统和方法

    公开(公告)号:US20170032854A1

    公开(公告)日:2017-02-02

    申请号:US15104971

    申请日:2015-01-16

    IPC分类号: G21C17/07

    CPC分类号: G21C17/07

    摘要: A method and system detects failures in nuclear fuel assemblies (600). A water treatment device degasses/removes fission gases from water used in the canister (500) of a vacuum sipping device (30). A sipping procedure then detects a failure in a fuel assembly in the canister. The degassing improves a signal-to-noise ratio of the detector used during the sipping process, and improves the failure detection sensitivity of the system. Additionally and/or alternatively, gas may be recirculated through the canister water before the vacuum is applied so that fission gas concentration in the recirculating gas reaches a baseline equilibrium with the canister water. The vacuum is thereafter applied and the sipping procedure proceeds such that an increase in detected radioactivity over the baseline equilibrium indicates a leak in the fuel assembly.

    摘要翻译: 一种方法和系统检测核燃料组件中的故障(600)。 水处理装置从真空吸取装置(30)的罐(500)中使用的水中除去/除去裂变气体。 然后,浸渍过程检测罐中的燃料组件中的故障。 脱气提高了在浸渍过程中使用的检测器的信噪比,并提高了系统的故障检测灵敏度。 另外和/或替代地,在施加真空之前,气体可以通过罐水再循环,使得再循环气体中的裂变气体浓度达到与罐水的基线平衡。 然后施加真空并且进行浸渍过程,使得检测到的放射性在基线平衡上的增加表示燃料组件中的泄漏。

    Leak detection method for testing fuel rods of fuel assemblies of a boiling water reactor for leaks
    34.
    发明授权
    Leak detection method for testing fuel rods of fuel assemblies of a boiling water reactor for leaks 有权
    用于检测沸水反应堆燃料组件燃料棒泄漏的泄漏检测方法

    公开(公告)号:US07778378B2

    公开(公告)日:2010-08-17

    申请号:US11801939

    申请日:2007-05-11

    IPC分类号: G21C17/00

    摘要: Fuel rods of fuel assemblies of a boiling water reactor are tested for leaks. A plurality of fuel assemblies are each arranged adjacent to one another in a cell of the upper core grid of the boiling water reactor. A hood is placed above a plurality of cells A water sample is taken from each of the cells, and the water samples from a plurality of cells forming a group are combined and tested for the presence of radioactive fission products A plurality of groups are analyzed simultaneously in a number, which number corresponds to the number of groups, of measurement channels. Where a result of a group is positive, the cells of the group are tested separately by the measurement channels. Those fuel assemblies of a cell that is found positive are tested individually outside the hood.

    摘要翻译: 测试沸水反应堆的燃料组件的燃料棒的泄漏。 多个燃料组件各自相邻布置在沸水反应堆的上部核心格栅的电池中。 将罩放置在多个细胞上方从每个细胞中取出水样,并且组合来自形成组的多个细胞的水样品并测试放射性裂变产物的存在。同时分析多个组 在一个数字中,哪个数字对应于组的数量,测量通道。 如果组的结果为正,则通过测量通道单独测试该组的单元。 发现阳性的电池的那些燃料组件在罩外单独测试。

    Process for electrochemical machining
    35.
    发明授权
    Process for electrochemical machining 失效
    电化学加工工艺

    公开(公告)号:US5516401A

    公开(公告)日:1996-05-14

    申请号:US271470

    申请日:1994-07-07

    摘要: An electrolyte is circulated between the surface to be machined, raised to an anode potential, and a tool electrode (9') raised to a cathode potential. The electrolyte contains lithium nitrate as a unique active product with a concentration of between 20 g/l and 2350 g/l and preferably between 50 g/l and 250 g/l. The process can be applied to the machining of the surface of any metallic component and in particular to the machining of the internal surface of tubular components (5) such as penetrations in the vessel bottom or closure head of a nuclear reactor; in this case the electrochemical machining cell consists of a cylindrical tool electrode (9') placed inside the component to be machined.

    摘要翻译: 电解质在待加工表面之间循环,升高至阳极电位,并将工具电极(9')升高至阴极电位。 电解液含有浓度为20g / l至2350g / l,优选为50g / l至250g / l的独特活性产物的硝酸锂。 该方法可以应用于任何金属部件的表面的加工,特别是加工管状部件(5)的内表面,例如在核反应堆的容器底部或封闭头中的穿透; 在这种情况下,电化学加工单元由放置在待加工部件内的圆柱形工具电极(9')组成。

    System for krypton-xenon concentration, separation and measurement for
rapid detection of defective nuclear fuel bundles
    36.
    发明授权
    System for krypton-xenon concentration, separation and measurement for rapid detection of defective nuclear fuel bundles 失效
    用于氪 - 氙浓度的系统,用于快速检测有缺陷的核燃料束的分离和测量

    公开(公告)号:US5457720A

    公开(公告)日:1995-10-10

    申请号:US228526

    申请日:1994-04-15

    摘要: A process and system for the rapid concentration, separation and measurement of Kr-85 and Xe-133. By measuring the amount of Kr-85 radioisotope which is present, false positive signals for the vacuum sipping process can be eliminated. The fission gases are trapped by passing the recirculating gas stream through an adsorbing media. During this process, a known mixture of nonradioactive krypton and xenon is added to the gas stream which enters a thermal conductivity (TC) detector to calibrate the latter. The trapped gases are desorbed and injected into the inlet of a separating column. The column discharges into the TC detector. The TC detector discharge is diverted for counting to an evacuated beta detector chamber during the time that krypton is sensed by the TC detector. Any minute amount of Kr-85 is captured in the chamber, free of Xe-133. The detector discharge is diverted for counting to another evacuated beta detector chamber during the time that xenon is sensed by the TC detector. Any minute amount of Xe-133 is captured in the chamber, free of Kr-85.

    摘要翻译: 用于快速浓缩,分离和测量Kr-85和Xe-133的方法和系统。 通过测量存在的Kr-85放射性同位素的量,可以消除真空吸收过程的假阳性信号。 裂解气体通过使再循环气流通过吸附介质而被捕获。 在此过程中,将已知的非放射性氪和氙混合物加入到进入热导率(TC)检测器以校准后者的气流中。 被捕获的气体被解吸并注入分离塔的入口。 该列排放到TC检测器中。 TC检测器放电在TC检测器感测氪时间内转向计数到抽空的β检测器室。 在室内捕获任何微量的Kr-85,不含Xe-133。 在TC检测器感测到氙时,检测器放电被转移到另一个抽空的β检测器室。 在室内捕获少量的Xe-133,不含Kr-85。

    Method of and an apparatus for the evaluation of burned-out nuclear fuel
elements
    37.
    发明授权
    Method of and an apparatus for the evaluation of burned-out nuclear fuel elements 失效
    燃烧核燃料元素评估方法和装置

    公开(公告)号:US4382906A

    公开(公告)日:1983-05-10

    申请号:US174171

    申请日:1980-07-31

    IPC分类号: G21C17/07 G21C17/00

    CPC分类号: G21C17/07

    摘要: Nuclear fuel elements or slugs are removed from the nuclear reactor cores and subjected to inspection, according to the invention, by introducing a plurality of such elements into a submerged inspection vessel which is then closed, the liquid driven out by compressed air and deionized water (deionate) circulated through the inspection vessel at a constant rate. A portion of the deionized water is branched from the circulating stream at a constant rate and the activity of at least one fission-product nuclide is determined continuously to plot the activity versus temperature, thereby signaling a possible defect in the shell of a fuel element. In addition, ultrasonic vibration is applied in the inspection vessel to the fuel elements so that deposits on the exterior thereof are released into the deionate whose circulating path includes a filter and an ion-exchange column for removal of such deposits.

    摘要翻译: 根据本发明,将核燃料元件或s塞从核反应堆堆芯中取出并进行检查,通过将多个这样的元件引入浸没的检查容器中,然后将其关闭,液体由压缩空气和去离子水( 爱好者)以恒定的速率循环通过检验船。 去离子水的一部分以恒定速率从循环流中分支,连续测定至少一个裂变产物核素的活性以绘制活性与温度的关系,从而发出燃料元件外壳中的可能缺陷。 此外,在检查容器中将超声波振动施加到燃料元件,使得其外部的沉积物被释放到循环路径包括过滤器和用于除去这些沉积物的离子交换柱的酸性物质中。

    Apparatus for detecting failure of the nuclear fuel rod
    38.
    发明授权
    Apparatus for detecting failure of the nuclear fuel rod 失效
    用于检测核燃料棒故障的装置

    公开(公告)号:US4318777A

    公开(公告)日:1982-03-09

    申请号:US85951

    申请日:1979-10-18

    IPC分类号: G21C17/06 G21C17/07 G21C17/00

    CPC分类号: G21C17/07

    摘要: An apparatus for detecting failure of the nuclear fuel rod has an outer cap and 16 (sixteen) inner caps. In checking for any faulty fuel rods, the outer cap is placed to cover the upper ends of 16 (sixteen) fuel assemblies mounted in the reactor core, while the inner caps in the outer cap are disposed on corresponding one of the fuel assemblies. To the outer cap are attached 4 (four) air supplying hoses. The inner caps receive corresponding one of 16 sampling tubes attached to the outer cap, and coolant sampling hoses are connected to the sampling tubes. A bundle member is fixed to the center of the upper surface of the outer cap. The four air supplying hoses and 16 coolant sampling hoses are fixed to the bundle member. The bundle member has a handle attached thereto.

    摘要翻译: 用于检测核燃料棒的故障的装置具有外盖和16(16)个内盖。 在检查任何有故障的燃料棒时,外盖被放置以覆盖安装在反应堆堆芯中的16(16)个燃料组件的上端,而外盖中的内盖设置在相应的一个燃料组件上。 外盖附有4(4)个供气软管。 内盖接收连接到外盖的16个采样管中的相应一个,并且冷却剂采样软管连接到采样管。 束构件固定在外盖的上表面的中心。 四个空气供应软管和16个冷却液取样软管固定到束构件上。 束构件具有附接到其上的手柄。

    Method of detecting leakage of radioactive gas from a nuclear fuel
assembly
    39.
    发明授权
    Method of detecting leakage of radioactive gas from a nuclear fuel assembly 失效
    检测核燃料组件放射性气体泄漏的方法

    公开(公告)号:US4248666A

    公开(公告)日:1981-02-03

    申请号:US903301

    申请日:1978-05-05

    申请人: Torsten Olsson

    发明人: Torsten Olsson

    IPC分类号: G21C17/07 G21C17/00

    CPC分类号: G21C17/07

    摘要: A method for simultaneously testing a plurality of fuel rod assemblies for leakage of radioactive gas, comprising the steps of removing the cover from a nuclear vessel containing the fuel rods, positioning a fixture over the fuel rods, reducing the hydrostatic pressure surrounding the fuel rods allowing gas to leak into the surrounding water, collecting water from about each fuel rod assembly in a separate chamber, separating gas from the water and testing the gas for the presence of radioactivity.

    摘要翻译: 一种用于同时测试多个用于放射性气体泄漏的燃料棒组件的方法,包括以下步骤:从包含燃料棒的核容器中移除盖,将夹具定位在燃料棒上,降低燃料棒周围的静水压力,从而允许 气体泄漏到周围的水中,在单独的室中从每个燃料棒组件周围收集水,将气体与水分离并测试气体以存在放射性。