公开(公告)号：US09020091B2

公开(公告)日：2015-04-28

申请号：US12102123

申请日：2008-04-14

申请人： Yong Lu ,  Xiaoyan Jiang

发明人： Yong Lu ,  Xiaoyan Jiang

IPC分类号： G21C3/34 ,  G21C3/352 ,  G21C3/356

CPC分类号： G21C3/352 ,  G21C3/3424 ,  G21C3/3566 ,  G21Y2002/20 ,  G21Y2002/302 ,  G21Y2002/303 ,  G21Y2004/301 ,  Y02E30/40

摘要： An improved grid for a nuclear reactor fuel assembly that has an egg-crate base grid as the primary support structure with each support cell of the base grid that supports a fuel rod having a lock-support sleeve that is rotatable within the support cell between a first and second orientation. In the first orientation the lock-support sleeve fits loosely within the support cell of the base grid and respectively, loosely receives the fuel rods that are loaded therein. The lock-support sleeves are then rotated to a second orientation that locks the fuel rods axially within the support cells.

摘要翻译： 一种用于核反应堆燃料组件的改进的电网，其具有蛋箱基栅格作为主支撑结构，其中基网格的每个支撑单元支撑燃料棒，所述燃料棒具有锁定支撑套筒，所述锁定支撑套筒可在支撑单元之间旋转， 第一和第二方向。 在第一方向上，锁定支撑套分别松动地配合在基座的支撑单元内，并且分别宽松地容纳加载在其中的燃料棒。 然后将锁定支撑套筒旋转到第二取向，将燃料棒轴向地锁定在支撑单元内。

公开(公告)号：US08345815B2

公开(公告)日：2013-01-01

申请号：US12192764

申请日：2008-08-15

申请人： Jürgen Stabel ,  Udo Borsdorf

发明人： Jürgen Stabel ,  Udo Borsdorf

IPC分类号： G21C3/34

CPC分类号： G21C3/322 ,  G21C3/352 ,  G21Y2002/20 ,  G21Y2004/302 ,  Y02E30/38

摘要： A fuel assembly for a pressurized water nuclear reactor contains a multiplicity of fuel rods which are guided in a plurality of axially spaced spacers which in each case form a square grid, composed of grid webs, with a multiplicity of cells arranged in rows and columns. In each case one control rod guide tube is guided through a number of these cells. At least one spacer is configured to be mechanically stronger in a first partial region than in a second partial region. In this second partial region, the spacer is provided with at least one resisting element which protrudes into a flow sub-channel formed between the fuel rods and increases the flow resistance. The resisting element counteracts a reduction associated with the mechanically weaker configuration, in the flow resistance in the second partial region and in this manner effects a homogenization of the hydraulic behavior of a spacer which is mechanically inhomogeneous on account of the varying mechanical configuration.

摘要翻译： 用于加压水核反应堆的燃料组件包含多个燃料棒，这些燃料棒在多个轴向隔开的间隔件中引导，每个间隔件在每种情况下形成由栅格网构成的方格栅格，多个单元以行和列排列。 在每种情况下，一个控制棒引导管被引导通过若干这些细胞。 至少一个间隔件构造成在第一部分区域中比在第二部分区域中机械地更强。 在该第二部分区域中，间隔件设置有至少一个抵抗元件，该抵抗元件突出到形成在燃料棒之间的流动子通道中并增加流动阻力。 抵抗元件抵消与机械较弱构造相关联的减小，在第二部分区域中的流动阻力中，并且以这种方式，由于变化的机械结构使得机械不均匀的间隔件的液压行为的均匀化。

公开(公告)号：US20090122945A1

公开(公告)日：2009-05-14

申请号：US12192764

申请日：2008-08-15

申请人： Jurgen Stabel ,  Udo Borsdorf

发明人： Jurgen Stabel ,  Udo Borsdorf

IPC分类号： G21C3/34

CPC分类号： G21C3/322 ,  G21C3/352 ,  G21Y2002/20 ,  G21Y2004/302 ,  Y02E30/38

摘要： A fuel assembly for a pressurized water nuclear reactor contains a multiplicity of fuel rods which are guided in a plurality of axially spaced spacers which in each case form a square grid, composed of grid webs, with a multiplicity of cells arranged in rows and columns. In each case one control rod guide tube is guided through a number of these cells. At least one spacer is configured to be mechanically stronger in a first partial region than in a second partial region. In this second partial region, the spacer is provided with at least one resisting element which protrudes into a flow sub-channel formed between the fuel rods and increases the flow resistance. The resisting element counteracts a reduction associated with the mechanically weaker configuration, in the flow resistance in the second partial region and in this manner effects a homogenization of the hydraulic behavior of a spacer which is mechanically inhomogeneous on account of the varying mechanical configuration.

摘要翻译： 用于加压水核反应堆的燃料组件包含多个燃料棒，这些燃料棒在多个轴向隔开的间隔件中引导，每个间隔件在每种情况下形成由栅格网构成的方格栅格，多个单元以行和列排列。 在每种情况下，一个控制棒引导管被引导通过若干这些细胞。 至少一个间隔件构造成在第一部分区域中比在第二部分区域中机械地更强。 在该第二部分区域中，间隔件设置有至少一个抵抗元件，该抵抗元件突出到形成在燃料棒之间的流动子通道中并增加流动阻力。 抵抗元件抵消与机械较弱构造相关联的减小，在第二部分区域中的流动阻力中，并且以这种方式，由于变化的机械结构使得机械不均匀的间隔件的液压行为的均匀化。

公开(公告)号：US20040228432A1

公开(公告)日：2004-11-18

申请号：US10437156

申请日：2003-05-13

发明人： Samuel W. Glass ,  Elton M. Crisman

IPC分类号： G21C017/00

CPC分类号： G21C17/003 ,  G21C17/017 ,  G21Y2002/20 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40

摘要： A combined laser and infra red sensing camera is located beneath the reactor head in the vicinity of the closure head tube welds by manipulating known robotic device handling the laser which is used to heat a line along the surface thereby generating a thermal wave that propagates over the one to two square inch test area where the increased thermal resistance of cracks and anomalies makes the surface temperature profile gradient greater at a crack or anomaly. An IR camera captures the test area image of interest as the thermal wave propagates across the target inspection area and the image is processed and enhanced to show cracks and other anomalies as a sharp drop in the thermal scan at the point of the crack using known Photo Thermal NDE technology to convert the scan into a pictorial representation of the scanned surface clearly showing any cracks therein. This process is repeated sequentially until the entire circumference of the weld is scanned.

摘要翻译： 组合的激光和红外线感测照相机位于封闭头管焊缝附近的反应器头下方，通过操纵已知的机器人装置来处理激光器，该激光器用于沿着表面加热一条线，从而产生传播超过 一到二平方英寸的试验区域，裂纹和异常增加的热阻使得表面温度分布梯度在裂纹或异常情况下更大。 红外摄像机捕获感兴趣的测试区域图像，因为热波传播到目标检测区域，并且图像被处理和增强，以显示裂纹和其他异常，因为裂纹点处的热扫描的急剧下降使用已知的照片 热扫描技术将扫描转换成扫描表面的图示，清晰显示其中有任何裂纹。 顺序重复该过程直到扫描焊缝的整个圆周。

公开(公告)号：US20030227991A1

公开(公告)日：2003-12-11

申请号：US10219610

申请日：2002-08-15

发明人： Young-Hwan Kang ,  Kee-Nam Choo ,  Bong-Goo Kim ,  Man-Soon Cho ,  Jae-Min Sohn ,  Do-Sik Kim ,  Jong-Man Park ,  Jong-Myeong Oh ,  Sung-Jae Park ,  Yoon-Taeg Shin

IPC分类号： G21G001/00

CPC分类号： G21C17/00 ,  G21C1/303 ,  G21Y2002/20 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/39

摘要： An instrumented capsule for material irradiation tests in research reactors. The instrumented capsule performs an optimum material irradiation test under a testing environment similar to the operational environment of a real reactor. The capsule minimizes the influence of flow-induced vibration caused by forced-circulation-type coolant flow in a research reactor, and overcomes the problems experienced in the conventional breakable parts of instrumented capsules which may be broken during the process of loading/unloading the capsules in vertical irradiation holes of reactor pools. The instrumented capsule includes a capsule main body installed in the vertical irradiation hole. The capsule main body consists of a shell and several instruments, such as thermocouples, dosimeters, a vacuum control pipe, and heaters housed in the shell. The capsule main body also includes heat media, specimens set in the heat media, insulators interposed between adjacent heat media, upper and lower end plugs to seal the ends of the shell, an upper guide spring unit to vertically place the capsule main body in the irradiation hole, and a reinforced lower fixing unit assembled with the lower end plug. The instrumented capsule also includes a connecting means for connecting the capsule main body to a capsule control system installed outside the reactor pool.

摘要翻译： 用于在研究堆中进行材料辐照测试的仪表胶囊。 仪器化胶囊在与实际反应器的操作环境相似的测试环境下进行最佳材料辐照试验。 胶囊将研究反应堆中由强制循环型冷却剂流引起的流动振动的影响最小化，并且克服了在装载/卸载胶囊的过程中可能破裂的仪器化胶囊的常规易碎部分中遇到的问题 在反应池的垂直照射孔中。 仪表胶囊包括安装在垂直照射孔中的胶囊主体。 胶囊主体由壳体和几个仪器组成，例如热电偶，剂量计，真空控制管和容纳在壳体中的加热器。 胶囊主体还包括热介质，设置在热介质中的试样，置于相邻热介质之间的绝缘体，用于密封外壳端部的上下端塞;上导向弹簧单元，用于将胶囊主体垂直放置在 照射孔和与下端塞组装的加强的下固定单元。 仪表胶囊还包括用于将胶囊主体连接到安装在反应池外部的胶囊控制系统的连接装置。

公开(公告)号：US5646971A

公开(公告)日：1997-07-08

申请号：US341980

申请日：1994-11-16

申请人： William F. Howe

发明人： William F. Howe

IPC分类号： G21C19/06

CPC分类号： G21C19/06 ,  G21Y2002/20 ,  G21Y2002/501 ,  G21Y2004/30 ,  G21Y2004/40 ,  G21Y2004/503

摘要： Apparatus for the underwater loading of nuclear materials into concrete containers employing heat removal systems includes a holding vessel and a cover. The holding vessel has a metal bottom and a metal outside wall which define an upwardly open cavity dimensioned to accommodate the concrete container while leaving a gap between the container and the outside wall. A cover covers this gap, while allowing access to the central open cavity of the container. Fasteners and seals fasten and seal the cover to the container and the holding vessel. A method for loading nuclear materials into such concrete containers, utilizing the apparatus of the subject invention, includes the steps of lifting the container into the steel vessel, lowering the cover into place, fastening and sealing the cover onto the container and vessel, and then lowering the container and vessel assembly into the water storage pool.

摘要翻译： 用于将核材料水下加载到使用散热系统的混凝土容器中的装置包括保持容器和盖子。 保持容器具有金属底部和金属外壁，其限定向上敞开的空腔，其尺寸适于容纳混凝土容器，同时在容器和外壁之间留下间隙。 盖子覆盖这个间隙，同时允许进入容器的中央开口腔。 紧固件和密封件将盖子固定并密封到容器和容器。 利用本发明的装置将核材料装载到这种混凝土容器中的方法包括以下步骤：将容器提升到钢容器中，将盖子放置到位，将盖子紧固并密封到容器和容器上，然后 将容器和容器组件降低到储水池中。

公开(公告)号：US5618356A

公开(公告)日：1997-04-08

申请号：US489597

申请日：1995-06-12

申请人： Ronald B. Adamson ,  Gerald A. Potts

发明人： Ronald B. Adamson ,  Gerald A. Potts

IPC分类号： C22F1/18 ,  G21C3/07

CPC分类号： C22F1/186 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/20 ,  G21Y2002/201 ,  G21Y2004/201 ,  Y02E30/40

摘要： In a zirconium-alloy fuel element cladding, a method for generating regions of coarse and fine intermetallic precipitates across the cladding wall is provided. The method includes steps of specific heat treatments and anneals that coarsen precipitates in the bulk of the cladding. The method also includes at least one step in which an outer region (exterior) of the cladding is heated to the beta or alpha plus beta phase, while an inner region (interior) is maintained at a temperature at which little or no metallurgical change occurs. This method produces a composite cladding in which the outer region comprises fine precipitates and the inner region comprises coarse precipitates.

摘要翻译： 在锆合金燃料元件包层中，提供了跨越包覆壁产生粗细和金属间析出物的区域的方法。 该方法包括在大部分包层中粗化析出物的特定热处理和退火步骤。 该方法还包括至少一个步骤，其中包层的外部区域（外部）被加热到β或α+β相，而内部区域（内部）保持在很少或不发生冶金变化的温度 。 该方法产生复合包层，其中外部区域包含微细的沉淀物，并且内部区域包括粗大的沉淀物。

公开(公告)号：US5468462A

公开(公告)日：1995-11-21

申请号：US161395

申请日：1993-12-06

申请人： Alistair I. Miller ,  Dino A. Spagnolo

发明人： Alistair I. Miller ,  Dino A. Spagnolo

IPC分类号： B01D59/32 ,  B01D59/40 ,  B01D59/50 ,  C01B4/00 ,  C01B5/02 ,  G21C19/30 ,  G21C19/307 ,  G21F9/02 ,  C01B5/00 ,  B01J8/00

CPC分类号： G21C19/307 ,  C01B4/00 ,  C01B5/02 ,  G21Y2002/20 ,  G21Y2004/20 ,  G21Y2004/30 ,  G21Y2004/40

摘要： A geographically distributed apparatus and process for detritiating heavy water is provided. The apparatus and process provide a remote site enrichment plant for producing an enriched stream of DT/D.sub.2 gas and a hydriding unit for forming a hydride of the DT/D.sub.2 gas for transportation. Pure tritium gas is produced at a local tritium extraction plant by reforming DT/D.sub.2 in a de-hydriding unit and passing the gas mixture through a chain of cryogenic distillation columns. The invention provides a safe and cost-effective method of detritiating heavy water.

摘要翻译： 提供了一种地理分布的装置和用于捣碎重水的方法。 该设备和方法提供了用于产生富集的DT / D2气体流的远程站点浓缩设备和用于形成用于运输的DT / D2气体的氢化物的氢化单元。 通过在去氢单元中重整DT / D2并使气体混合物通过一系列低温蒸馏塔，在当地的氚萃取厂生产纯氚气体。 本发明提供了一种安全且具有成本效益的破坏重水的方法。

公开(公告)号：US5383226A

公开(公告)日：1995-01-17

申请号：US977032

申请日：1992-11-16

申请人： Roland Deleryd ,  Gunnar Stahl

发明人： Roland Deleryd ,  Gunnar Stahl

IPC分类号： G21C17/07 ,  G21C17/00

CPC分类号： G21C17/07 ,  G21Y2002/20 ,  G21Y2002/304 ,  G21Y2002/40 ,  G21Y2004/30 ,  G21Y2004/40

摘要： During leak detection of fuel assemblies (10) for a boiling water nuclear reactor, water is sucked from an area (12) located above an outlet (11) for water from the fuel assembly and around a gripper (8) for a loading machine (1) for fuel assemblies, which gripper is secured to the fuel assembly above the outlet, while the fuel assembly is lifted in the water (6) in which the fuel assembly is immersed or while the fuel assembly, after having been lifted in the water, is maintained in its lifted position or relowered in the water and while maintaining a flow of the water through the fuel assembly and around the gripper. The sucked-off water is subjected to an analysis with respect to the presence of fission products which, during operation of the reactor, have been formed of the fuel in the fuel assembly.

摘要翻译： 在用于沸水核反应堆的燃料组件（10）的泄漏检测期间，从位于出口（11）上方的区域（12）中的水被从燃料组件和用于装载机的夹具（8）周围的水吸入， 1）用于燃料组件，其中夹持器在出口上方固定到燃料组件，同时燃料组件在其中浸入燃料组件的水（6）中升起，或者在燃料组件在水中被提升之后被提升 保持在其提升位置或在水中回流并且同时保持水通过燃料组件和夹持器周围的流动。 对吸入的水进行关于在反应器运行期间由燃料组件中的燃料形成的裂变产物的存在的分析。

公开(公告)号：US5375150A

公开(公告)日：1994-12-20

申请号：US175308

申请日：1993-12-29

申请人： Kenneth Scarola ,  David S. Jamison ,  Richard M. Manazir ,  Robert L. Rescorl ,  Daryl L. Harmon

发明人： Kenneth Scarola ,  David S. Jamison ,  Richard M. Manazir ,  Robert L. Rescorl ,  Daryl L. Harmon

IPC分类号： G05B9/03 ,  G21C17/00 ,  G21D3/00 ,  G21D3/04

CPC分类号： G05B23/027 ,  G05B9/03 ,  G21C17/00 ,  G21D3/00 ,  G21D3/008 ,  G21D3/04 ,  G21Y2002/20 ,  G21Y2002/201 ,  G21Y2002/203 ,  G21Y2002/206 ,  G21Y2002/207 ,  G21Y2002/208 ,  G21Y2002/50 ,  G21Y2004/30 ,  G21Y2004/40 ,  G21Y2004/401 ,  Y02E30/39 ,  Y04S10/522

摘要： The use of alarm indication on the overview (IPSO) display to initiate diagnosis of challenges to critical functions or unavailability of success paths, and further alarm-based guidance toward ultimate diagnosis.

摘要翻译： 在概述（IPSO）显示屏上使用报警指示来启动对关键功能的挑战的诊断或成功路径的不可用性，以及进一步的基于报警的最终诊断指导。