-
1.发明授权Nuclear reactor primary system chemical decontamination clean-up system component arrangement 失效核反应堆主要系统化学净化清理系统组件安排
公开(公告)号：US5491732A
公开(公告)日：1996-02-13
申请号：US989420
申请日：1992-12-11
申请人： Gary J. Corpora , Phillip E. Miller , Thomas G. Bengel , Frank I. Bauer , Dan H. Dixon , James Sejvar
发明人： Gary J. Corpora , Phillip E. Miller , Thomas G. Bengel , Frank I. Bauer , Dan H. Dixon , James Sejvar
CPC分类号： G21D1/02 , G21C19/28 , G21Y2002/301 , G21Y2002/501 , G21Y2004/30 , G21Y2004/60 , Y02E30/40
摘要： A nuclear reactor having a chemical decontamination clean-up system is provided in which every component of the chemical decontamination clean-up equipment which processes radioactive fluids is located within a shielded room of an existing on-site support building. Those components of the clean-up system not in direct contact with radioactive fluids are housed in portable trailers. The decontamination clean-up system is designed to provide for adequate shielding to minimize personnel exposure and also incorporates a modular design for component transportation and storage.
摘要翻译： 提供了具有化学去污清理系统的核反应堆，其中处理放射性流体的化学净化清理设备的每个部件位于现有现场支持建筑物的屏蔽室内。 不与放射性液体直接接触的清理系统的部件安装在便携式拖车中。 净化清理系统旨在提供足够的屏蔽以尽量减少人员接触，并且还包含组件运输和存储的模块化设计。
-
公开(公告)号：US5046289A
公开(公告)日：1991-09-10
申请号：US307103
申请日：1989-02-06
摘要： System and method for abrading radioactive contaminants from the inside surface of a pipe. The system includes a nozzle block capable of mixing a liquid and an abrasive grit into a suitable liquid-abrasive grit cleaning composition and impinging the cleaning composition against the inside surface of the pipe. The system further includes an inflatable torus-shaped seal for confining the liquid-abrasive grit cleaning composition to a predetermined portion of the inside surface of the pipe so that substantially all of the contaminants and cleaning composition can be suitably vacuumed from the surface.
摘要翻译： 从管内表面研磨放射性污染物的系统和方法。 该系统包括能够将液体和磨料砂粒混合到合适的液体磨料砂粒清洁组合物中并将清洁组合物抵靠在管的内表面上的喷嘴块。 该系统还包括一个可膨胀的环形密封件，用于将液体磨料砂粒清洁组合物限制在管子内表面的预定部分，使得基本上所有的污染物和清洁组合物都可以从表面被适当地抽真空。
-
3.发明授权Temporary hot cell and related method for handling high radiation level sources 失效临时热电池及相关处理高辐射源的方法
公开(公告)号：US4876593A
公开(公告)日：1989-10-24
申请号：US158009
申请日：1988-02-19
IPC分类号： G21F7/03
CPC分类号： G21F7/03
摘要： A temporary hot cell and related method for handling high radiation level sources having wall, ceiling and floor structures comprised at least in part of temporary structures forming an enclosure to reduce to acceptable levels radiation of the surround from high level radiation sources handled within the enclosure. Preferably one or more manipulator arms extended through a wall structure of the enclosure to permit handling of the high level radiation sources within the enclosure by an operator located external to the enclosure. A window is positioned in the wall structure of the enclosure to allow an external operator to view handling of the radiation sources. The hot cell preferably also has a false floor, a filter and vent system sheeting to cover portions of the inner surface of the temporary structure forming the enclosure hot cell.
摘要翻译： 一种用于处理具有墙壁，天花板和地板结构的高辐射水平源的临时热电池和相关方法，其包括至少部分临时结构，形成外壳，以将外壳中的高级辐射源的环绕辐射降低到可接受的水平。 优选地，一个或多个操纵器臂延伸穿过外壳的壁结构，以允许位于外壳外部的操作者处理外壳内的高级辐射源。 窗口被定位在外壳的壁结构中，以允许外部操作者观察辐射源的处理。 热电池还优选地还具有假地板，过滤器和通风系统，以覆盖形成封闭热电池的临时结构的内表面的部分。
-
公开(公告)号：US09466399B2
公开(公告)日：2016-10-11
申请号：US12715420
申请日：2010-03-02
申请人： James Sejvar
发明人： James Sejvar
摘要： An expansion gap radiation shield is formed from a flexible container housing a radiation shielding fluid, that is located within a variable gap in permanent shielding. The invention reduces radiation dose rates outside the gap when the radiation sources are located on the opposite side of the gap. The device accommodates varying gap sizes with no loss of shielding capability.
摘要翻译： 膨胀间隙辐射屏蔽由容纳辐射屏蔽流体的柔性容器形成，辐射屏蔽流体位于永久屏蔽中的可变间隙内。 当辐射源位于间隙的相对侧时，本发明减小了间隙外的辐射剂量率。 该装置适应不同的间隙尺寸，而不损失屏蔽能力。
-
公开(公告)号：US5009836A
公开(公告)日：1991-04-23
申请号：US368433
申请日：1989-06-19
申请人： Noel P. Grimm , James Sejvar
发明人： Noel P. Grimm , James Sejvar
摘要： A first plurality of water filled shielding tanks is introduced through a nuclear reactor containment building hatch and placed between the stored core internals and the reactor vessel. A support structure for this vertical wall is previously shipped, disassembled, introduced into containment and erected between the reactor vessel and the stored internals. A second plurality of water filled shielding tanks is placed on the containment building operating floor level to cover the stored internals. Once in place, the tanks allow manned activity in the reactor vessel area, such as preparations for annealing. The method includes the steps of: removing the nuclear fuel from the reactor; storing both the upper and lower internals underwater; assembling the support structure and placing same in position in the refueling canal; introducing the vertical and horizontal tanks through the hatch; filling the vertical shielding tanks with water and placing same in the support structure; filling the horizontal shielding tanks with water and placing them above the stored internals and the vertical tanks; draining water from the refueling canal to the level of the reactor vessel flange; performing an operation requiring human intervention such as annealing; flooding the refueling canal to near the operating floor elevation; and decontaminating the tanks and support structure and removing same.
-
公开(公告)号：US4844858A
公开(公告)日：1989-07-04
申请号：US32861
申请日：1987-03-31
IPC分类号： G21C17/003
CPC分类号： G21C17/003
摘要： A reactor cavity dosimetry system and method in a nuclear power plant having a reactor vessel and a primary biological shield substantially surrounding the reactor vessel thereby forming a reactor cavity between the vessel and the shield, the system and method providing for remotely and repeatedly positioning a plurality of neutron dosimeters at preselected locations within the cavity, and for withdrawing the dosimeters for analysis thereof and replacing them at the same preselected positions. Assessment of the long-term effects of neutron irradiation on the vessel is enhanced by accurate and repetitive placement of the dosimeters.
摘要翻译： 核动力装置中的反应堆腔剂量测定系统和方法，其具有基本上围绕反应器容器的反应器容器和初级生物屏蔽，从而在容器和屏蔽之间形成反应器空腔，所述系统和方法提供远程和重复定位多个 的中子剂量计在腔内的预选位置处，并且用于取出用于分析的剂量计并在相同的预选位置替换它们。 通过准确和重复放置剂量计，可以增强中子照射对血管的长期影响。
-
公开(公告)号：US20100296618A1
公开(公告)日：2010-11-25
申请号：US12715420
申请日：2010-03-02
申请人： James Sejvar
发明人： James Sejvar
IPC分类号： G21C9/00
摘要： An expansion gap radiation shield is formed from a flexible container housing a radiation shielding fluid, that is located within a variable gap in permanent shielding. The invention reduces radiation dose rates outside the gap when the radiation sources are located on the opposite side of the gap. The device accommodates varying gap sizes with no loss of shielding capability.
摘要翻译： 膨胀间隙辐射屏蔽由容纳辐射屏蔽流体的柔性容器形成，辐射屏蔽流体位于永久屏蔽中的可变间隙内。 当辐射源位于间隙的相对侧时，本发明减小了间隙外的辐射剂量率。 该装置适应不同的间隙尺寸，而不损失屏蔽能力。
-
8.发明授权
公开(公告)号：US5699394A
公开(公告)日：1997-12-16
申请号：US502236
申请日：1995-07-13
申请人： Roger B. Schreiber , Arnold H. Fero , James Sejvar
发明人： Roger B. Schreiber , Arnold H. Fero , James Sejvar
CPC分类号： G21C11/08 , G21C15/18 , G21Y2002/40 , Y02E30/40
摘要： The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.
摘要翻译： 在反应堆空腔中从冷腿喷嘴悬挂的核反应堆装置的反应堆容器设置有与反应器容器隔开的下部隔热屏障，以形成可以通过无源阀充满冷却水直至冷却的室 发生严重事故的反应堆船只。 被动阀还包括用于释放蒸汽的隔热屏障上端的双稳态通风口。 一个可拆卸的模块化中子屏蔽层，围绕喷嘴下方的反应器空腔的上端延伸，形成反应堆容器外表面上的向上和向外的锥形过渡，迷宫式通道，减少中子流动，同时为逃逸提供通道 在严重事故期间的蒸汽，以及在反应堆的正常操作期间沿着隔热屏障外部的反应堆空腔壁循环的冷却空气。
-
-
-
-
-
-
-
搜索结果
8 条记录 (耗时 0.036 秒)
