Electrical connector assembly, test lead assembly therefor, and associated method
    1.
    发明授权
    Electrical connector assembly, test lead assembly therefor, and associated method 有权
    电气连接器组件,测试引线组件及相关方法

    公开(公告)号:US08206186B2

    公开(公告)日:2012-06-26

    申请号:US12634913

    申请日:2009-12-10

    IPC分类号: H01R11/18

    摘要: A test lead assembly is provided for an electrical connector assembly, such as a terminal board. The terminal board includes a generally planar member and a number of fasteners, such as terminal screws, which are structured to fasten and electrically connect electrical conductors to the generally planar member. The test lead assembly includes an extension member having first and second opposing ends, and an intermediate portion extending therebetween. The first end is fastened to the enlarged head of a corresponding one of the terminal screws. A connection element is disposed at or about the second end of the extension member. In one embodiment the connection element is a thumb screw that electrically connects a test element to the extension member. The test lead assembly enables the terminal board to be tested, without loosening or otherwise disturbing the electrical connections of the terminal board. An associated method is also disclosed.

    摘要翻译: 为电连接器组件(例如端子板)提供测试导线组件。 端子板包括大致平面的构件和多个紧固件,例如端子螺钉,其被构造成将电导体紧固并电连接到大体上平坦的构件。 测试导线组件包括具有第一和第二相对端的延伸构件和在它们之间延伸的中间部分。 第一端紧固到相应的一个端子螺钉的扩大头部。 连接元件设置在延伸构件的第二端处或周围。 在一个实施例中,连接元件是将测试元件电连接到延伸构件的指旋螺钉。 测试导线组件能够对端子板进行测试,而不会松动或以其他方式干扰端子板的电气连接。 还公开了一种相关联的方法。

    Method of applying a burnable poison onto the exterior of nuclear rod cladding
    2.
    发明授权
    Method of applying a burnable poison onto the exterior of nuclear rod cladding 有权
    将可燃毒物应用于核棒包层外部的方法

    公开(公告)号:US07815964B2

    公开(公告)日:2010-10-19

    申请号:US11692952

    申请日:2007-03-29

    IPC分类号: A61M36/14 G21C3/06

    摘要: A method for applying a burnable poison onto the cladding of a nuclear fuel rod (2) which comprises, providing a nuclear fuel rod (2) and at least one application device (8), rotating the nuclear fuel rod, optionally removing one or more oxides and/or surface deposits on the outer surface of the nuclear fuel rod (2) by spraying an abrasive material onto the nuclear fuel rod via the application device (8) while adjusting the position of the application device in relation to the nuclear fuel rod (2), and applying burnable poison particles (33) onto the outer surface (6) of the nuclear fuel rod (2) by spraying the burnable poison onto the nuclear fuel rod via the application device while adjusting the position of the application device (8) in relation to the nuclear fuel rod, where the burnable poison particles are applied at a velocity sufficient to cause adhesion to the outer surface (6) of the cladding.

    摘要翻译: 一种将可燃毒物施加到核燃料棒(2)的包层上的方法,包括:提供核燃料棒(2)和至少一个施加装置(8),旋转核燃料棒,任选地去除一个或多个 通过经由施加装置(8)将研磨材料喷射到核燃料棒上,同时调整施加装置相对于核燃料棒的位置,从而在核燃料棒(2)的外表面上沉积氧化物和/或表面沉积物 (2),并且通过在施加装置的位置调整的同时通过施加装置将可燃毒物喷射到核燃料棒上,将可燃毒物颗粒(33)施加到核燃料棒(2)的外表面(6) 8)相对于核燃料棒,其中以足以引起粘附到包层的外表面(6)的速度施加可燃毒物颗粒。

    Permanent seal ring for a nuclear reactor cavity
    3.
    发明授权
    Permanent seal ring for a nuclear reactor cavity 有权
    用于核反应堆腔的永久密封环

    公开(公告)号:US07813464B1

    公开(公告)日:2010-10-12

    申请号:US11952358

    申请日:2007-12-07

    IPC分类号: G21C13/00

    CPC分类号: G21C13/028 Y02E30/40

    摘要: A permanent cavity seal ring that replaces the function of the temporary cavity seal ring typically used in narrow thermal expansion gap pressurized water reactors, to seal the gap between the reactor cavity well and the reactor during refueling. The permanent seal ring uses a C-shaped flexure that is shielded by a rigid cantilevered support arm from any accidentally dropped equipment from above in the refueling canal. The construction accommodates the thermal expansion of the reactor vessel while permitting the reactor cavity cooling air to exit the annulus between the vessel and the reactor cavity wall during plant operation, without a significant increase in pressure drop.

    摘要翻译: 永久性腔密封环,其代替通常用于窄热膨胀间隙加压水反应器中的临时空腔密封环的功能,以在加油期间密封反应堆腔与反应器之间的间隙。 永久性密封环使用C形弯曲,其由刚性悬臂支撑臂从加油管中的任何意外掉落的设备从上方被屏蔽。 该结构适应反应堆容器的热膨胀,同时允许反应器腔冷却空气在工厂操作期间离开容器和反应器空腔壁之间的环空,而不会显着增加压降。

    Method of assessing the performance of a steam generator
    4.
    发明授权
    Method of assessing the performance of a steam generator 有权
    评估蒸汽发生器性能的方法

    公开(公告)号:US07726169B2

    公开(公告)日:2010-06-01

    申请号:US11669194

    申请日:2007-01-31

    IPC分类号: G01D18/00

    CPC分类号: F22B37/002

    摘要: A grading system for a pressurized water reactor steam generator secondary side performance that provides a cumulative assessment of tube bundle deposit inventory and characteristics, i.e., scale density and distribution, hard scale collar formation, thermal performance, loose parts management, and steam generator secondary side chemistry performance. Results are summarized in a cumulative quality point average with individual parameter ratings available so that specific performance improvement may be achieved.

    摘要翻译: 一种压水反应堆蒸汽发生器二次侧性能分级系统,提供管束沉积物库存和特性的累积评估,即尺度密度和分布,硬质合金圈形成,热性能,松散零件管理和蒸汽发生器二次侧 化学性能。 结果总结在累积质量点平均值中,具有可用的各个参数等级,以便可以实现特定的性能改进。

    Over temperature and over power delta temperature operating margin recovery method and reactor system employing the same
    6.
    发明授权
    Over temperature and over power delta temperature operating margin recovery method and reactor system employing the same 有权
    过温和过功率三角洲温度运行裕度恢复方法和采用该方法的反应堆系统

    公开(公告)号:US07596198B1

    公开(公告)日:2009-09-29

    申请号:US11367001

    申请日:2006-03-02

    IPC分类号: G21C17/00

    CPC分类号: G21C9/00 G21D3/04 Y02E30/40

    摘要: A method is provided for recovering operating margin in a nuclear reactor. The reactor includes a steam generator, a Reactor Coolant System (RCS) having a hot leg with a temperature, Thot, and a cold leg with a temperature, Tcold, a Reactor Trip System (RTS) having an Over Temperature Delta Temperature (OTDT) trip function and an Over Power Delta Temperature (OPDT) trip function, and a control system. The method improves the RTS by filtering only the hot leg temperature signal of the RCS. Thus, the needs for separate Tavg and Delta-T filters, and for filtering of temperature signals in both the hot leg and cold leg are eliminated. A reactor system is also disclosed.

    摘要翻译: 提供了一种用于回收核反应堆运行余量的方法。 反应器包括蒸汽发生器,具有温度的热腿的反应器冷却剂系统(RCS),具有温度Tcold的冷腿,具有过温度差温度(OTDT)的反应器跳闸系统(RTS)), 跳闸功能和过功率增量温度(OPDT)跳闸功能,以及控制系统。 该方法通过仅对RCS的热腿温度信号进行过滤来改善RTS。 因此,消除了单独的Tavg和Delta-T滤波器以及用于过滤热腿和冷腿中的温度信号的需要。 还公开了一种反应器系统。

    Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys
    7.
    发明授权
    Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys 有权
    从腌制锆铌合金中去除铌第二相颗粒沉积物

    公开(公告)号:US07468106B2

    公开(公告)日:2008-12-23

    申请号:US11682981

    申请日:2007-03-07

    IPC分类号: C23G1/00

    CPC分类号: C23G1/106 C23G1/36

    摘要: The present invention provides a method for removing niobium-rich second-phase-particle (SPP) deposits from zirconium-niobium alloy components. The method comprises washing a freshly pickled and rinsed zirconium-niobium alloy component with an acidified oxalic acid or ammonium oxalate washing solution. The method of the present invention results in a rapid, efficient and complete removal of surface SPP deposits from the zirconium-niobium alloy component without pitting, leaving behind a clean, shiny surface without the need to use water blasting or mechanical wiping operations.

    摘要翻译: 本发明提供了一种从锆 - 铌合金组分中除去富含铌的第二相颗粒(SPP)沉积物的方法。 该方法包括用酸化的草酸或草酸铵洗涤溶液洗涤新鲜酸洗和漂洗的锆 - 铌合金组分。 本发明的方法能够快速,有效和完全地从锆 - 铌合金组分中除去表面SPP沉积物,而无需点蚀,留下清洁光泽的表面,而无需使用喷砂或机械擦拭操作。

    Spectroscopy-based safety system and method for a vacuum arc remelt furnace
    8.
    发明授权
    Spectroscopy-based safety system and method for a vacuum arc remelt furnace 有权
    基于光谱的安全系统和真空电弧再熔炉的方法

    公开(公告)号:US07257145B2

    公开(公告)日:2007-08-14

    申请号:US11143178

    申请日:2005-06-02

    IPC分类号: H05B7/148

    摘要: A vacuum arc remelt furnace system that automatically monitors for electrode to crucible arcing in a VAR furnace. The vacuum arc remelt furnace system includes a crucible, an electrode provided within the crucible, and a spectrometer operatively coupled to the gap between the electrode and the crucible. The spectrometer detects the presence of one or more copper-specific light wavelengths in light that is present in the gap, and preferably generates an alarm and/or shuts the furnace down depending upon what is detected. Also, a method of operating a vacuum arc remelt furnace to automatically monitor for electrode top crucible arcing. The method includes collecting light that is present in the gap between the crucible and said electrode, and determining whether one or more copper-specific light wavelengths are present in the light. An alarm is generated and/or the furnace is shut down depending upon what is detected.

    摘要翻译: 一种真空电弧再熔炉系统,可自动监测VAR炉中的电极和坩埚电弧。 真空电弧再熔炉系统包括坩埚,设置在坩埚内的电极和可操作地耦合到电极和坩埚之间的间隙的光谱仪。 光谱仪检测存在于间隙中的光中存在一种或多种铜特定的光波长,并且优选地根据所检测的内容产生报警和/或关闭炉。 另外,一种操作真空电弧再熔炉的方法来自动监测电极顶坩埚电弧。 该方法包括收集存在于坩埚和所述电极之间的间隙中的光,以及确定光中是否存在一种或多种铜特定的光波长。 根据检测到的内容,产生报警和/或炉关闭。

    Method and algorithm for searching and optimizing nuclear reactor core loading patterns
    9.
    发明授权
    Method and algorithm for searching and optimizing nuclear reactor core loading patterns 有权
    核反应堆核心装载模式的搜索和优化方法和算法

    公开(公告)号:US07224761B2

    公开(公告)日:2007-05-29

    申请号:US10993249

    申请日:2004-11-19

    申请人: Frank D. Popa

    发明人: Frank D. Popa

    IPC分类号: G21C19/00

    摘要: A method is for establishing a nuclear reactor core loading pattern (LP) for fuel assemblies and burnable absorbers (BAs). The method establishes an optimum LP through the steps of: a) providing nuclear data representing fuel assemblies and BAs in a nuclear reactor core; b) depleting the nuclear data to form a reference core depletion; c) incorporating the nuclear data into a system of linear equations of a nuclear design quality flux solution method; d) defining the system of linear equations to include constraints which accurately represent the neutron physics of the reactor; employing the equations as a constraint matrix for a MIP solver to find an optimum core pattern solution; f) repeating steps b) through e) updating the constraints and objective functions to satisfy specified engineering requirements and establish an optimum core loading pattern. An algorithm for deriving the system of equations is also disclosed.

    摘要翻译: 一种用于建立燃料组件和可燃吸收器(BAs)的核反应堆堆芯装载模式(LP)的方法。 该方法通过以下步骤建立最佳LP:a)在核反应堆核心中提供代表燃料组件和BAs的核数据; b)消耗核数据以形成参考核心耗尽; c)将核数据纳入核设计质量通量溶液法线性方程组; d)定义线性方程组,以包括精确表示反应堆中子物理学的约束; 采用方程作为MIP求解器的约束矩阵以找到最佳核心图案解; f)重复步骤b)至e)更新约束和目标函数以满足规定的工程要求并建立最佳的核心加载模式。 还公开了用于导出方程组的算法。

    Device and method for ultrasonic inspection using profilometry data
    10.
    发明授权
    Device and method for ultrasonic inspection using profilometry data 有权
    使用轮廓测量数据进行超声波检测的装置和方法

    公开(公告)号:US07194908B2

    公开(公告)日:2007-03-27

    申请号:US11031841

    申请日:2005-01-07

    IPC分类号: G01N29/26

    摘要: An ultrasonic testing assembly structured to examine a test object, wherein the test object has a surface, and the examination examines the structure of the test object under the surface as well as the profile of the surface. The ultrasonic testing assembly includes a sled assembly structured to support a plurality of ultrasonic transducers, the sled assembly including at least one support member having a lower surface, at least one surface ultrasonic transducer coupled to the sled assembly and structured to extend below the support member lower surface and further structured to engage the test object surface, the surface ultrasonic transducer structured to examine internal structure of the test object and provide a first output, at least one profiling device coupled to the sled assembly, the profiling device structured to measure the profile of the test object surface and provide a second output, and a control device structured to correlate the first output and the second output and to calculate a corrected output.

    摘要翻译: 一种构造成检查被测物体的超声波测试组件,其中测试对象具有表面,并且检查检查表面下的测试对象的结构以及表面的轮廓。 超声波测试组件包括构造成支撑多个超声波换能器的滑动组件,滑动组件包括至少一个具有下表面的支撑构件,至少一个表面超声波换能器,其耦合到滑动组件并被构造成在支撑构件下方延伸 所述表面超声波换能器被构造成检查所述测试对象的内部结构,并提供第一输出,耦合到所述滑动组件的至少一个剖析装置,所述剖面装置构造成测量所述剖面 并提供第二输出,以及控制装置,其被构造为使第一输出和第二输出相关并且计算校正输出。