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    • 1. 发明授权
    • Method for using an underwater milling machine
    • 水下铣床的使用方法
    • US5097583A
    • 1992-03-24
    • US616097
    • 1990-11-20
    • Arthur W. KramerEdward H. Smith
    • Arthur W. KramerEdward H. Smith
    • B23C1/20G21C19/02
    • G21C19/02B23C1/20G21C19/207Y10T29/49726Y10T29/5108Y10T408/5612Y10T409/303808
    • A machining system for performing heavy duty milling and other repair operations under water is disclosed herein which is particularly useful in performing repair and maintenance operations in the core barrels of nuclear reactors. The machining system generally comprises a platform, a machining device which is detachably connectable to the platform which includes a drive motor and cutter necessary to effect the repair or maintenance operation, and a triaxial adjustment mechanism which permits the machine cutter to be precisely positioned at any desired location within the core barrel. The platform has a guide mechanism which includes both a rough and a fine guide means which precisely positions the machining device with respect to the platform when it is lowered thereon. A hydraulically operated lock remotely and detachably secures the machining device into position on the platform after the guide mechanism has properly positioned it. The platform is advantageously designed to be secured onto a component within the core barrel having a known and precise alignment with respect to the other core barrel components, such as the support lugs of the thermal shield, which in turn provides a mechanical reference point for the machine cutter attached to the platform.
    • 本文公开了一种用于在水下执行重型铣削和其他修复操作的加工系统,其特别可用于在核反应堆的核心桶中进行修理和维护操作。 该加工系统通常包括平台,可拆卸地连接到平台的加工装置,该平台包括执行修理或维护操作所需的驱动马达和切割器;以及三轴调节机构,其允许机床切割器精确地定位在任何 核心筒内所需的位置。 平台具有引导机构,其包括粗略和精细引导装置,其在加工装置降低时相对于平台精确地定位加工装置。 在导向机构正确定位之后,液压操作的锁远程地和可拆卸地将加工装置固定在平台上的适当位置。 该平台有利地被设计成被固定在芯筒内的部件上,其具有相对于另一个芯部筒部件(例如热屏蔽件的支撑凸耳)的已知且精确的对准,其又提供了用于 机刀连接在平台上。
    • 2. 发明授权
    • Underwater milling machine system for core barrel repair
    • 水下铣床系统用于核心桶维修
    • US5001818A
    • 1991-03-26
    • US251694
    • 1988-09-30
    • Arthur W. KramerEdward H. Smith
    • Arthur W. KramerEdward H. Smith
    • B23C1/20G21C19/02
    • B23C1/20G21C19/02G21C19/207Y10T29/5108Y10T408/5612Y10T408/91Y10T409/306216Y10T409/309912
    • A machining system for performing heavy duty milling and other repair operations under water is disclosed herein which is particularly useful in performing repair and maintenance operations in the core barrels of nuclear reactors. The machining system generally comprises a platform, a machining device which is detachably connectable to the platform which includes a drive motor and cutter necessary to effect the repair or maintenance operation, and a triaxial adjustment mechanism which permits the machine cutter to be precisely positioned at any desired location within the core barrel. The platform has a guide mechanism which includes both a rough and a fine guide means which precisely positions the machining device with respect to the platform when it is lowered thereon. A hydraulically operated lock remotely and detachably secures the machining device into position on the platform after the guide mechanism has properly positioned it. The platform is advantageously designed to be secured onto a component within the core barrel having a known and precise alignment with respect to the other core barrel components, such as the support lugs of the thermal shield, which in turn provides a mechanical reference point for the machine cutter attached to the platform.
    • 本文公开了一种用于在水下执行重型铣削和其他修复操作的加工系统,其特别可用于在核反应堆的核心桶中进行修理和维护操作。 该加工系统通常包括平台,可拆卸地连接到平台的加工装置,该平台包括执行修理或维护操作所需的驱动马达和切割器;以及三轴调节机构,其允许机床切割器精确地定位在任何 核心筒内所需的位置。 平台具有引导机构,其包括粗略和精细引导装置,其在加工装置降低时相对于平台精确地定位加工装置。 在导向机构正确定位之后,液压操作的锁远程地和可拆卸地将加工装置固定在平台上的适当位置。 该平台有利地被设计成被固定在芯筒内的部件上,其具有相对于另一个芯部筒部件(例如热屏蔽件的支撑凸耳)的已知且精确的对准,其又提供了用于 机刀连接在平台上。
    • 3. 发明授权
    • Method and tooling for dismantling, casking and removal of nuclear reactor core structures
    • 核反应堆核心结构的拆除,包装和清除的方法和工具
    • US07668281B2
    • 2010-02-23
    • US11623864
    • 2007-01-17
    • Leonard J. BalogThomas A. HackleyArthur W. Kramer
    • Leonard J. BalogThomas A. HackleyArthur W. Kramer
    • G21C19/00
    • G21C19/20G21C19/32G21C19/34G21D1/003Y02E30/40Y02W30/881
    • A method is provided for removing radioactive internals structural members in the core of a reactor pressure vessel in a containment vessel. The method includes placing a first cask in a first internals assembly, detaching radioactive first internals structural members from second internals structural members in the first internals assembly, placing the detached first internals structural members in the first cask, placing the first internals assembly in a second cask, and removing the second cask containing the first internals assembly and containing the casked detached radioactive first internals members from the containment vessel. The first internal members may be radioactive baffle plates, and the second internals members may be former plates bolted to the radioactive baffle plates. Novel tooling, framework and fixtures facilitate disassembling, moving and storing the radioactive baffle plates.
    • 提供了一种用于去除安全壳中的反应堆压力容器的核心中的放射性内部结构构件的方法。 该方法包括将第一桶放置在第一内件组件中,从第一内件组件中的第二内部结构件分离放射性第一内部结构构件,将分离的第一内部结构构件放置在第一桶中,将第一内件组件放置在第二内件组件中 并且将包含第一内件组件的第二个容器移出并且从容纳容器中包含已经分离的放射性第一内部构件。 第一内部构件可以是放射性挡板,并且第二内部构件可以是螺栓连接到放射性挡板的前板。 新型工具,框架和夹具有助于拆卸,移动和存放放射性挡板。
    • 4. 发明申请
    • METHOD AND TOOLING FOR DISMANTLING, CASKING AND REMOVAL OF NUCLEAR REACTOR CORE STRUCTURES
    • 核反应堆核心结构的分离,分离和去除的方法与工具
    • US20090285345A1
    • 2009-11-19
    • US11623864
    • 2007-01-17
    • Leonard J. BalogThomas A. HackleyArthur W. Kramer
    • Leonard J. BalogThomas A. HackleyArthur W. Kramer
    • G21C19/00
    • G21C19/20G21C19/32G21C19/34G21D1/003Y02E30/40Y02W30/881
    • A method is provided for removing radioactive internals structural members in the core of a reactor pressure vessel in a containment vessel. The method includes placing a first cask in a first internals assembly, detaching radioactive first internals structural members from second internals structural members of the first internals assembly, placing the detached first internals structural members in the first cask, placing the first internals assembly in a second cask, and removing the second cask containing the first internals assembly and containing the casked detached radioactive first internals members from the containment vessel. The first internal members may be radioactive baffle plates, and the second internals members may be former plates bolted to the radioactive baffle plates. Novel tooling, framework and fixtures facilitate disassembling, moving and storing the radioactive baffle plates.
    • 提供了一种用于去除安全壳中的反应堆压力容器的核心中的放射性内部结构构件的方法。 该方法包括将第一桶放置在第一内件组件中,从第一内件组件的第二内部结构件分离放射性第一内部结构构件,将分离的第一内部结构构件放置在第一桶中,将第一内件组件放置在第二内件组件中 并且将包含第一内件组件的第二个容器移出并且从容纳容器中包含已经分离的放射性第一内部构件。 第一内部构件可以是放射性挡板,并且第二内部构件可以是螺栓连接到放射性挡板的前板。 新型工具,框架和夹具有助于拆卸,移动和存放放射性挡板。
    • 7. 发明授权
    • Non-bolted ringless nozzle dam
    • 非螺栓无环喷嘴坝
    • US4637588A
    • 1987-01-20
    • US605354
    • 1984-04-30
    • John J. WilhelmGregory L. CalhounPaul H. DawsonArthur W. Kramer
    • John J. WilhelmGregory L. CalhounPaul H. DawsonArthur W. Kramer
    • F22B1/06F16L55/136F22B37/00F22B37/02F22B37/22F16K31/44F16L55/12
    • F16L55/136F22B37/222Y10S277/921
    • A nozzle dam for providing a fluid-tight seal across a primary fluid nozzle in the plenum of a nuclear steam generating vessel includes an elongated shaft coupled at one end thereof to an anchor assembly frictionally engageable with the inner surface of the nozzle to anchor the dam in place and a fluid-impermeable seal apparatus coupled to the shaft and closing the nozzle and frictionally engageable with the inner surface thereof to form a fluid-tight seal. The seal apparatus includes a circular plate disposable in wedging frictional engagement with a frustoconical portion of the nozzle inner surface. The shaft extends through a central aperture in the plate and is threadedly engaged with a nut which holds the plate in place. The anchor assembly includes a foldable tripod arrangement coupled to the shaft in such a way that movement of the shaft toward the seal plate effects an increase in the frictional anchoring force. The seal assembly also includes an inflatable portion. In one embodiment this inflatable portion extends around the perimeter of the seal plate and is readily expandable. In another embodiment the inflatable portion includes inflatable pillows disposed between the seal plate and the anchor assembly and inflatable for completely closing the nozzle. A foldable tripod centering mechanism and a shaft tensioning tool are also disclosed.
    • 用于在核蒸汽发生容器的气室中的主流体喷嘴上提供流体密封的喷嘴坝包括在其一端处联接到锚固组件的细长轴,其与喷嘴的内表面摩擦接合以锚定坝 并且液体不可渗透的密封装置联接到轴并且关闭喷嘴​​并与其内表面摩擦接合以形成流体密封。 密封装置包括与喷嘴内表面的截头圆锥形部分楔入摩擦接合的圆形板。 轴延伸穿过板中的中心孔,并与固定板的螺母螺纹接合。 锚固组件包括以这样的方式联接到轴的可折叠的三脚架装置,使得轴朝向密封板的运动影响摩擦锚定力的增加。 密封组件还包括可充气部分。 在一个实施例中,该可充气部分围绕密封板的周边延伸并且易于扩张。 在另一个实施例中,可膨胀部分包括设置在密封板和锚固组件之间的可充气枕头,并可充气以完全关闭喷嘴。 还公开了可折叠的三脚架定心机构和轴张紧工具。
    • 9. 发明授权
    • System and method for removing and consolidation fuel rods of a nuclear
fuel assembly
    • 用于拆卸和整合核燃料组件的燃料棒的系统和方法
    • US4952072A
    • 1990-08-28
    • US311435
    • 1989-02-16
    • Frederick J. EllingsonAnoop KapoorArthur W. KramerDonald G. Sherwood
    • Frederick J. EllingsonAnoop KapoorArthur W. KramerDonald G. Sherwood
    • G21C19/34
    • G21C19/34
    • A system and a method for removing and consolidating the spent fuel rods of a fuel assembly is disclosed herein. The sytem comprises a pushing assembly having a push rod for pushing a selected fuel rod out of a fuel assembly, a fuel assembly positioner including an elevator for conveniently positioning a fuel assembly within the spent fuel pool of a nuclear facility, a rod catching grid for preventing the pushed-out fuel rods from falling to the bottom of the pool and a transition cannister for funneling the rods into a consolidated arrangement within a storage cannister. In operation, the push rod is positioned over and engaged against the upper end of a fuel rod to be removed from the assembly. Thus engaged, the push rod is inserted through the cells in the grids of the fuel assembly that surround the selected fuel rod, thereby pushing it out of the fuel assembly. Thus the grid cells are used as an alignment means for the push rod during the rod-pushing operation.
    • 本文公开了一种用于去除和固结燃料组件的乏燃料棒的系统和方法。 该系统包括具有用于将选定的燃料棒推出燃料组件的推杆的推动组件,包括用于将燃料组件方便地定位在核设施的乏燃料池内的电梯的燃料组件定位器,用于 防止被推出的燃料棒落到池底部;以及过渡罐,用于将棒料斗放入储存罐内的固结装置中。 在操作中,推杆定位在燃料棒的上端并与其接合以从组件移除。 因此,推杆通过围绕选定燃料棒的燃料组件的格栅中的电池插入,从而将其推出燃料组件。 因此,网格单元在推杆操作期间用作推杆的对准装置。