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    • 8. 发明申请
    • Passive System for Cooling the Core of a Nuclear Reactor
    • 用于冷却核反应堆核心的被动系统
    • US20160118147A1
    • 2016-04-28
    • US14918665
    • 2015-10-21
    • WESTINGHOUSE ELECTRIC COMPANY LLC
    • Alexander W. Harkness
    • G21C15/18
    • G21C15/18G21C19/07G21D3/06Y02E30/32
    • A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days.
    • 一种用于在加油期间在加压水反应堆中被动地冷却核燃料的系统,其使用蓄电池储备的重力和对准阀或在安全位置构型中失效,以在反应堆拆卸和加油期间将水保持在反应堆堆芯上方。 大量储备的水被保持在废燃料池的高度和流体连通之外,并且在核心中的反应已经成功地停止之后被用于去除反应堆堆芯的腐蚀热。 通过煮沸大量储备的水来消除朽烂的热量,这将使得工厂能够在没有外部支持的情况下保持安全关闭条件多天。
    • 9. 发明申请
    • WATER-AIR COMBINED PASSIVE FEED WATER COOLING APPARATUS AND SYSTEM
    • 水 - 空气组合被动进料水冷却装置和系统
    • US20150243383A1
    • 2015-08-27
    • US14287551
    • 2014-05-27
    • KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    • Tae-Soon KWONKihwan KIMHyun Sik PARKSung Won BAEYusun PARK
    • G21C15/18
    • G21C15/18G21C2015/185G21D3/06Y02E30/40
    • Disclosed herein is a water-air combined passive feed water cooling apparatus including a water cooling heat exchanger connected to the inside of a containment building to cool down heat of a steam generator using a water cooling method, a cooling tank including the water cooling heat exchanger therein and storing cooling water condensing main steam generated by the steam generator, an evaporative steam pipe connected to the cooling tank, the evaporative steam pipe, into which steam of the cooling water generated by the water cooling heat exchanger in the cooling tank flows, an air cooling heat exchanger connected to the evaporative steam pipe and cooling down and liquefying the steam flowing into the evaporative steam pipe, and a condensed water collecting pipe for refilling the cooling tank with the steam liquefied by the air cooling heat exchanger.
    • 本发明公开了一种水 - 空气组合无源给水冷却装置,其包括连接到容纳建筑物的内部的水冷式热交换器,以使用水冷方式冷却蒸汽发生器的热量,包括水冷却热交换器 存储由蒸汽发生器产生的冷凝水主蒸汽,连接到冷却罐的蒸发蒸汽管,蒸发蒸汽管,由冷却罐中的水冷却热交换器产生的冷却水的蒸汽流动, 连接到蒸发蒸气管的空气冷却热交换器,冷却并液化流入蒸发蒸汽管的蒸汽,以及冷凝水收集管,用于通过空气冷却热交换器液化的蒸汽来重新填充冷却罐。
    • 10. 发明申请
    • REACTOR CONTAINMENT PRESSURE SUPPRESSION
    • 反应器容纳压力抑制
    • US20150194226A1
    • 2015-07-09
    • US14170727
    • 2014-02-03
    • Babcock & Wilcox mPower, Inc.
    • Robert P MartinMichael J Edwards
    • G21C11/00
    • G21C13/02G21C9/004G21D3/06Y02E30/40
    • A nuclear reactor is surrounded by a reactor radiological containment structure. A spent fuel pool is adjacent to and outside of the reactor radiological containment structure. The spent fuel pool may also be contained in its own radiological containment structure. A valved steam pipe runs from the reactor containment structure into the spent fuel pool. During a reactor containment overpressure event, a valve on the steam pipe is opened to allow steam from the reactor containment structure to discharge into (e.g. sparge into) the spent fuel pool. In an alternative embodiment suitable for use in a two-pack nuclear power plant, steam pipes connect the reactor radiological containment structures of the two nuclear reactors, and isolation valves on the steam pipes are opened in response to an overpressure condition in one reactor containment structure in order to discharge steam into the other reactor containment structure.
    • 一个核反应堆被一个反应堆放射性遏制结构所包围。 废燃料池与反应堆放射性容纳结构相邻并且在其外部。 乏燃料池也可能包含在其自身的放射性遏制结构中。 有阀门的蒸汽管道从反应堆容纳结构延伸到乏燃料池中。 在反应堆容纳超压事件期间,蒸汽管上的阀打开以允许来自反应堆容纳结构的蒸汽排放到(例如喷射)废燃料池中。 在适用于双组件核电站的替代实施例中,蒸汽管连接两个核反应堆的反应堆放射性容纳结构,并且响应于一个反应堆容纳结构中的超压状况而打开蒸汽管上的隔离阀 以将蒸汽排放到另一个反应堆容纳结构中。