Angle beam ultrasonic probe for internal hex socket bolts

    公开(公告)号:US09689845B2

    公开(公告)日:2017-06-27

    申请号:US13894535

    申请日:2013-05-15

    申请人: AREVA Inc.

    摘要: A tool for inspecting the integrity of fasteners in their environment of use and methods of performing such inspections are disclosed and claimed. The tool includes a probe that matches the internal socket by which the fastener is coupled to the workpiece. The probe contains ultrasonic transducers on flat portions corresponding to flat portions of the socket. The transducers induce angled ultrasonic beams into the fastener to detect flaws therein. The beams are angled so they can be directed to the areas of interest at the head to shank region of the fastener. The presence of a defect such as a crack is determined based on the reply/echoes of the imparted ultrasonic beams.

    SEALING DEVICE FOR JET PUMP SLIP JOINTS
    2.
    发明申请

    公开(公告)号:US20170108013A1

    公开(公告)日:2017-04-20

    申请号:US14885109

    申请日:2015-10-16

    申请人: AREVA Inc.

    IPC分类号: F04F5/46 G21C15/25 F04F5/10

    摘要: A sealing device for a jet pump of a boiling water reactor is provided. The jet pump includes an inlet mixer and a diffuser receiving the inlet mixer at a slip joint such that an outer circumferential surface of the inlet mixer is received in an inner circumferential surface of the diffuser at the slip joint. The diffuser includes a plurality of guiding fins, each guiding fin including a radially inner surface, a radially outer surface and lateral surfaces extending radially between the inner and outer surfaces. The sealing device includes a seal configured for sealingly contacting the outer circumferential surface of the inlet mixer and a collar configured for holding the seal against the outer circumferential surface of the inlet mixer. The collar includes portions configured for being received radially between the radially inner surfaces of the guiding fins and the outer circumferential surface of the inlet mixer. The sealing device further includes a clamp configured for contacting the radially outer surfaces of the guiding fins to axially clamp the guiding fins. A method of mounting a sealing device onto a slip joint of a jet pump of a boiling water reactor is also provided.

    Boiling water reactor core shroud head bolt retainer tool

    公开(公告)号:US09393680B2

    公开(公告)日:2016-07-19

    申请号:US14724230

    申请日:2015-05-28

    申请人: AREVA Inc.

    发明人: Jason B. Cocke

    IPC分类号: B25B27/02 B23P19/04 G21C19/20

    摘要: The inventive tool is designed to ensure proper plant operation position of the core shroud head bolt assemblies of a boiling water nuclear reactor. The tool exerts an upward pulling force on stuck retainers to return them to the locking position around the nut. The tool includes a frame, an engagement member, and a collar. The engagement member is lowered toward and end of the bolt until it comes into contact therewith. Further movement of the engagement member causes the frame and collar to move upward, lifting the retainer and extending the spring.

    Boiling Water Reactor Core Shroud Head Bolt Retainer Tool
    4.
    发明申请
    Boiling Water Reactor Core Shroud Head Bolt Retainer Tool 有权
    沸水反应堆核心护套头螺栓固定工具

    公开(公告)号:US20150340107A1

    公开(公告)日:2015-11-26

    申请号:US14724230

    申请日:2015-05-28

    申请人: AREVA Inc.

    发明人: Jason B. Cocke

    IPC分类号: G21C19/20 B23P19/04

    摘要: The inventive tool is designed to ensure proper plant operation position of the core shroud head bolt assemblies of a boiling water nuclear reactor. The tool exerts an upward pulling force on stuck retainers to return them to the locking position around the nut. The tool includes a frame, an engagement member, and a collar. The engagement member is lowered toward and end of the bolt until it comes into contact therewith. Further movement of the engagement member causes the frame and collar to move upward, lifting the retainer and extending the spring.

    摘要翻译: 本发明的工具被设计成确保沸水核反应堆的核心护罩头部螺栓组件的适当的工厂操作位置。 工具对卡住的保持器施加向上的拉力,以将它们返回到螺母周围的锁定位置。 该工具包括框架,接合构件和套环。 接合构件朝向螺栓的端部降下,直到其与其接触。 接合构件的进一步移动使得框架和套环向上移动,提升保持器并延伸弹簧。

    Immobilization of Technetium by Electroless Plating
    5.
    发明授权
    Immobilization of Technetium by Electroless Plating 有权
    通过无电解电镀固定锝

    公开(公告)号:US09108867B2

    公开(公告)日:2015-08-18

    申请号:US13964247

    申请日:2013-08-12

    申请人: AREVA Inc.

    发明人: Kevin J. Hagerty

    摘要: A process of incorporating technetium into an electroless deposit, forming an alloy that is extremely resistant to corrosion and reduces the mobility of technetium on a geologic time scale is disclosed and claimed. The process includes providing a liquid containing technetium, such as an aqueous waste stream generated during the used nuclear fuel reprocessing activities. The technetium is collected and concentrated, and provided into an electroless deposition bath. A substrate, such as suitably prepared zero valent iron or stainless steel, is introduced into the bath to initiate autocatalytic electroless deposition of the technetium onto the substrate due to the difference in electrochemical potential between the plating bath and the metals in solution. This causes a layer of technetium metal to form on the substrate. The electroless deposition is continued until virtually all of the technetium has been removed from the bath, and then continues to build a layer of technetium-free material on the outermost surface of the substrate. One or more additional deposition steps may be performed to armor the plated substrate against leaching/corrosion in a nuclear waste disposal facility.

    摘要翻译: 公开并要求保护将锝掺入无电沉积物中的方法,形成非常耐腐蚀的合金并降低锝在地质时间尺度上的流动性。 该方法包括提供含有锝的液体,例如在使用的核燃料后处理活动期间产生的废水。 将锝收集并浓缩,并提供到无电沉积浴中。 由于镀液与溶液中的金属之间的电化学势的差异,将诸如适当制备的零价铁或不锈钢的衬底引入浴中以引发锝在衬底上的自动催化无电沉积。 这会在基板上形成一层锝金属。 无电沉积继续,直到几乎所有的锝已经从浴中除去,然后继续在基底的最外表面上构建一层无锝材料。 可以执行一个或多个附加的沉积步骤以使镀覆的衬底防止在核废物处理设备中的浸出/腐蚀。

    METHOD OF PEENING AN OBSTRUCTED REGION OF A METAL ASSEMBLY

    公开(公告)号:US20190226049A1

    公开(公告)日:2019-07-25

    申请号:US16337525

    申请日:2016-10-03

    申请人: AREVA INC.

    摘要: A method for peening an obstructed region of a metal assembly that is obstructed by an obstructing part of the metal assembly is provided. The method includes determining an optimal peening path for treating the obstructed region irrespective of the obstructing part; identifying a portion of the obstructing part within the optimal peening path; determining a section of the portion of the obstructing part that is removable without affecting a mechanical integrity and functionality of the obstructing part; removing, by machining, the section so as to create additional space along the optimal peening path; and peening the obstructed region, a path of the peening at least partially crossing through the additional space. A method for peening a nuclear reactor pressure vessel is also provided.

    Control rod drive mechanism outer diameter seal ultra high pressure cavitation peening

    公开(公告)号:US10163533B2

    公开(公告)日:2018-12-25

    申请号:US14554525

    申请日:2014-11-26

    申请人: AREVA Inc.

    IPC分类号: C21D7/06 G21C19/00 C21D10/00

    摘要: A sealing device is provided to form a sealed region about one or more surfaces to be treated. The sealing device has an open end with a rim configured to matingly engage a treatment surface. The sealing device is braced both vertically and laterally, and the sealed region is flooded and pressurized. A peening nozzle and manipulating tooling are positioned within an interior volume of the sealing device. Pressurized fluid is ejected from the nozzle causing the formation of cavitation bubbles. The nozzle flow causes the cavitation bubbles to settle on the surfaces to be treated. The collapsing impact of the cavitation bubbles imparts compressive stress in the materials of the treatment surfaces.

    PROBABILISTIC EVALUATION OF FASTENER DEGRADATION IN NUCLEAR POWER PLANTS

    公开(公告)号:US20170337298A1

    公开(公告)日:2017-11-23

    申请号:US15158851

    申请日:2016-05-19

    申请人: AREVA Inc.

    IPC分类号: G06F17/50 G06N7/00 G06F17/18

    摘要: A probabilistic method for determining an operability interval for fasteners in a nuclear power plant assembly is provided. The probabilistic method includes determining or assuming a geometric distribution of a given initial condition of fasteners in the nuclear power plant assembly at an initial time T0; determining a future fastener failure probability model of the geometric distribution over time; generating a plurality of random future fastener failure patterns by applying the fastener failure model to the geometric distribution at a given time T1>T0; postulating fastener spacing rules designed to evaluate the acceptability of fastener failure patterns for the fasteners in the nuclear power plant assembly; applying the fastener spacing rules to a plurality of randomly generated fastener failure patterns for the given time T1 to determine the probability of the randomly generated fastener failure patterns passing the fastener spacing rules at the given time T1; iterating, by a processor of a computer, the applying step for a given range of time values T2, T3, . . . , Tx>T0 and determining a maximum future time Tmax at which a predetermined acceptable probability of the fastener failure patterns passing the fastener spacing rules is met, thereby justifying the acceptability of the fasteners for continued operation of the nuclear power plant assembly; and determining the operability interval as being Tmax-T0.