Nuclear power generation system
    3.
    发明授权

    公开(公告)号:US09922740B2

    公开(公告)日:2018-03-20

    申请号:US14437897

    申请日:2013-10-25

    Abstract: A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant.

    NUCLEAR POWER GENERATION SYSTEM
    5.
    发明申请
    NUCLEAR POWER GENERATION SYSTEM 有权
    核发电系统

    公开(公告)号:US20150255181A1

    公开(公告)日:2015-09-10

    申请号:US14437897

    申请日:2013-10-25

    Abstract: A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop. This creates a temperature differential between the primary and secondary coolant sufficient to create natural thermally induced convective circulation of the primary coolant

    Abstract translation: 在一个实施例中,公开了核发电系统和相关的动力循环,该系统包括通过包含核燃料的液压互连反应堆的主要冷却剂循环和共同限定蒸汽供应系统的蒸汽发生容器。 用于动力循环的液体二次冷却剂流过蒸汽发生容器,并通过主冷却剂转化为蒸汽以驱动涡轮发电机组的低压涡轮机。 离开涡轮机的蒸汽在返回到蒸汽供应系统之前被冷凝和加热,从而完成二次冷却剂流动循环。 在一个实施例中,二次冷却剂加热的大部分通过与主冷却剂的热交换而不是在二次冷却剂流动回路中的外部在蒸汽发生容器内发生。 这在初级冷却剂和次级冷却剂之间产生了温差,足以产生主冷却剂的自然热诱导的对流循环

    RADIOACTIVE CAPTURE SYSTEM FOR SEVERE ACCIDENT CONTAINMENT OF LIGHT WATER REACTORS (LWRS), AND METHOD THEREOF
    6.
    发明申请
    RADIOACTIVE CAPTURE SYSTEM FOR SEVERE ACCIDENT CONTAINMENT OF LIGHT WATER REACTORS (LWRS), AND METHOD THEREOF 有权
    用于严重意外容纳轻水反应堆(LWRS)的放射性捕获系统及其方法

    公开(公告)号:US20140161218A1

    公开(公告)日:2014-06-12

    申请号:US13710766

    申请日:2012-12-11

    Abstract: A system and a method for capturing gaseous, particulate and liquid radioactive material released from primary containment of a Light Water Reactor (LWR) during severe accident conditions. The system includes a below-grade media area, connected to a reactor pressure vessel (RPV) and portions of primary containment, providing varying levels of adsorption/absorption of the radioactive material. The media area is located on-site to offer a passive, self-regulating structure for stabilizing a nuclear reactor. The capture system provides for liquid drainage and gaseous venting of the radioactive material, and a treatment capable of treating the media following stabilization of the reactor.

    Abstract translation: 一种在严重事故条件下捕获从轻水反应堆(LWR)初级容纳物释放的气态,颗粒状和液体放射性物质的系统和方法。 该系统包括连接到反应堆压力容器(RPV)的低级介质区域和初级容纳部分,提供放射性物质的吸附/吸收的不同水平。 媒体区域位于现场,提供用于稳定核反应堆的被动,自调节结构。 捕获系统提供放射性物质的液体排放和气体排放,以及在反应器稳定后能够处理介质的处理。

    Building with a sealing element
    7.
    发明授权
    Building with a sealing element 失效
    建筑用密封元件

    公开(公告)号:US5791107A

    公开(公告)日:1998-08-11

    申请号:US442804

    申请日:1995-05-17

    Abstract: The invention pertains to a building, particularly in the context of a nuclear installation. The building is formed with an outer shell and an inner shell which form an intermediate space therebetween. A sealing element is disposed in the intermediate space. The sealing element is gas tight, it envelopes the inner shell, and it is largely freely movable perpendicularly to the surfaces of the shells defining the intermediate space. Pressure fluctuations, particularly pressure waves, originating on the inside of the building are received and equalized by the sealing element, while the gas-tightness of the sealing element is largely assured.

    Abstract translation: 本发明涉及一种建筑物,特别是在核设施的背景下。 该建筑物形成有在其间形成中间空间的外壳和内壳。 密封元件设置在中间空间中。 密封元件是气密的,它包封内壳,并且它大体上可自由地垂直于限定中间空间的壳体的表面移动。 起始于建筑物内部的压力波动,特别是压力波被密封元件容纳并均衡,同时密封元件的气密性大大保证。

    Protection system for the basemat reactor containment buildings in
nuclear power stations
    8.
    发明授权
    Protection system for the basemat reactor containment buildings in nuclear power stations 失效
    核电站基地反应堆容器建筑保护系统

    公开(公告)号:US5057271A

    公开(公告)日:1991-10-15

    申请号:US508074

    申请日:1990-04-10

    CPC classification number: G21C9/016 G21C13/10 Y02E30/40

    Abstract: A protection system for the basemat of reactor containment buildings in nuclear power stations. The system comprises a structure located in a cavity below the reactor vessel and submerged in water. The structure comprises staggered layers of stainless steel beams for intercepting molten material escaping from the reactor vessel during meltdown of the reactor core. The system is designed so that the molten material is distributed in thin layers over wings of the beams and transfers its heat to the surrounding water thus affording a rapid quenching of the molten core and safeguarding the integrity of the basemat.

    Nuclear power plant providing a function of suppressing the deposition
of radioactive substance
    10.
    发明授权
    Nuclear power plant providing a function of suppressing the deposition of radioactive substance 失效
    提供抑制放射性物质沉积功能的核电站

    公开(公告)号:US4722823A

    公开(公告)日:1988-02-02

    申请号:US525889

    申请日:1983-08-24

    CPC classification number: G21C13/087 G21C13/10 Y02E30/40

    Abstract: A nuclear power plant using a structural material consisting of metal which comes into contact with a liquid in which radioactive substances are dissolved has a function to suppress the deposition of the radioactive substances. In this function, metal elements constituting the surface layer of the structural material which comes into contact with the liquid are oxidized by injecting oxidizing agents from outside, thereby preliminarily producing an oxide film. The oxidizing agents comprise at least one kind selected from the group consisting of oxygen, hydrogen peroxide, chromate, nitrite, molybdate, tungstate and ferrate. Particularly, by suppressing the deposition of radioactive substances on a stainless steel, the dose rate of exposure of workers is effectively reduced.

    Abstract translation: 使用与溶解有放射性物质的液体接触的金属构成的结构材料的核电站具有抑制放射性物质沉积的功能。 在该功能中,构成与液体接触的结构材料的表面层的金属元素通过从外部注入氧化剂而被氧化,从而预先生成氧化膜。 氧化剂包括选自氧,过氧化氢,铬酸盐,亚硝酸盐,钼酸盐,钨酸盐和高铁酸盐中的至少一种。 特别是通过抑制放射性物质在不锈钢上的沉积,有效地降低了工作人员的接触剂量。

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