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    NUCLEAR POWER PLANT
    2.
    发明申请
    NUCLEAR POWER PLANT 审中-公开
    核电站

    公开(公告)号：US20160189809A1

    公开(公告)日：2016-06-30

    申请号：US14607760

    申请日：2015-01-28

    Applicant: CAVERION Deutschland GmbH

    Inventor： Chafik El Kabali ,  Hans Felser ,  Peter Hausch ,  Claus Schweinheim

    IPC: G21C9/004

    CPC classification number: G21C9/004 ,  G21C13/02 ,  G21C19/303 ,  G21F9/02 ,  Y02E30/40

    Abstract: The invention relates to a nuclear power plant including a containment vessel including a reactor pressure vessel for receiving fissionable nuclear fuel, an aerosol filter stage a pressure relief conduit through which a gas volume flow which is filtered in the aerosol filter stage is releasable to ambient through a pass through opening in the containment vessel, and an iodine filter stage through which the gas volume flow that is filtered in the aerosol filter stage is filterable before being released to the ambient, wherein the iodine filter stage is arranged within the containment vessel, characterized in that the aerosol filter stage and the iodine filter stage are connected with one another so that transferring the gas volume flow from the aerosol filter stage to the iodine filter stage is performed essentially at an identical pressure level.

    Abstract translation: 本发明涉及一种核动力装置，其包括容纳容器，其包括用于接收可裂变核燃料的反应堆压力容器，气溶胶过滤器级，在气溶胶过滤器阶段中过滤的气体体积流量通过该压力释放导管可释放到环境通过 在安全壳中通过开口，以及碘过滤器阶段，在气溶胶过滤器阶段过滤的气体体积流量在被释放到环境之前是可过滤的，其中碘过滤器级布置在安全壳内，其特征在于 因为气溶胶过滤器级和碘过滤器级彼此连接，使得将气体体积流从气溶胶过滤器阶段转移到碘过滤器阶段基本上在相同的压力水平下进行。

    Nuclear plant with a containment shell and with a pressure relief system
    3.
    发明申请
    Nuclear plant with a containment shell and with a pressure relief system 审中-公开
    具有遏制壳和压力释放系统的核工厂

    公开(公告)号：US20150243379A1

    公开(公告)日：2015-08-27

    申请号：US14593250

    申请日：2015-01-09

    Applicant: AREVA GMBH

    Inventor： SEBASTIAN BUHLMANN ,  BERND ECKARDT ,  NORBERT LOSCH

    IPC: G21C9/004 ,  G21C19/303 ,  G21C13/02

    CPC classification number: G21C9/004 ,  G21C9/06 ,  G21C13/02 ,  G21C19/303 ,  G21C19/317 ,  Y02E30/31

    Abstract: A nuclear plant has a containment shell and a pressure relief line passing out of the containment shell and sealed by a shut-off valve, and through which a pressure relief flow can flow during relief operation, such that it is configured for particularly reliable management of critical scenarios where there is a considerable pressure increase within the containment shell at the same time as the release of hydrogen and/or carbon monoxide. A gas flow treatment device is provided upstream from the respective pressure relief line, and contains a flow duct and has a lower inflow opening and an upper inflow/outflow opening. Catalytic elements for eliminating hydrogen and/or carbon monoxide are arranged in the flow duct above the lower inflow opening. During a critical fault, the flow duct is flowed through from bottom to top by a gas mixture present in the containment shell by the principle of natural convection.

    Abstract translation: 一个核电厂有一个安全壳和一个压力释放管线，通过安全壳外壳并被一个截止阀密封，并且在卸压操作过程中，泄压流可以流过，从而使其被配置成特别可靠地管理 在释放氢气和/或一氧化碳的同时，在容纳壳内存在相当大的压力增加的关键情况。 气体流量处理装置设置在相应的压力释放线的上游，并且包含流动管道，并且具有较低的流入开口和上部流入/流出开口。 用于消除氢气和/或一氧化碳的催化元素被布置在下流入口上方的流动管道中。 在严重故障期间，通过自然对流的原理，流动管道通过存在于安全壳中的气体混合物从下到上流动。

    Corrosion preventing device for in-pile structures of helium gas-cooled reactor
    8.
    发明授权
    Corrosion preventing device for in-pile structures of helium gas-cooled reactor 失效
    氦气冷却反应堆桩内结构防锈装置

    公开(公告)号：US4610841A

    公开(公告)日：1986-09-09

    申请号：US582519

    申请日：1984-02-22

    Applicant: Masao Yamada ,  Haruo Kawakami

    Inventor： Masao Yamada ,  Haruo Kawakami

    IPC: G21C19/303 ,  G21C9/00

    CPC classification number: G21C19/303

    Abstract: A corrosion preventing device for use in an in-pile structure of a helium gas-cooled reactor for removing gaseous oxidating components from a primary cooling gas in a pressure vessel of the reactor to thus prevent oxidation of graphite members of the reactor pile. An oxidation product consuming member is provided in series with a primary cooling gas supply pipeline or a bypass pipeline thereof along with a device for heating the oxidation product consuming member. The oxidation product consuming member may be a single cylindrical member or a bundle of rods having a large number of through holes formed therein in a honeycomb pattern in the lengthwise direction thereof or a large number of balls. The material of the oxidation product consuming member should have a high affinity for oxidizing impurities at elevated temperatures. Preferably, the material of the oxidation product consuming member is carbon or graphite.

    Abstract translation: 一种用于氦气冷却反应堆的堆叠结构的防腐蚀装置，用于从反应堆的压力容器中的一级冷却气体中除去气态氧化组分，从而防止反应堆堆石墨的氧化。 与主要冷却气体供应管线或其旁路管道串联地提供氧化产物消耗构件以及用于加热氧化产物消耗构件的装置。 氧化产物消耗部件可以是单个的圆柱形部件或具有在其长度方向上以蜂窝状图案形成的大量通孔的大量的棒或大量的球。 氧化产物消耗部件的材料应在高温下对于氧化杂质具有高亲和力。 优选地，氧化产物消耗部件的材料是碳或石墨。

    Process and system for removing tritium
    10.
    发明授权
    Process and system for removing tritium 失效
    移除三角形的过程和系统

    公开(公告)号：US3937649A

    公开(公告)日：1976-02-10

    申请号：US411249

    申请日：1973-10-31

    Applicant: John N. Ridgely

    Inventor： John N. Ridgely

    IPC: G21C19/303 ,  G21C17/00

    CPC classification number: G21C19/303

    Abstract: A process and system for removing tritium, particularly from high temperature gas cooled atomic reactors (HTGR), is disclosed. Portions of the reactor coolant, which is permeated with the pervasive tritium atom, are processed to remove the tritium. Under conditions of elevated temperature and pressure, the reactor coolant is combined with gaseous oxygen, resulting in the formation of tritiated water vapor from the tritium in the reactor coolant and the gaseous oxygen. The tritiated water vapor and the remaining gaseous oxygen are then successively removed by fractional liquefaction steps. The reactor coolant is then re-circulated to the reactor.

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