会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 4. 发明专利
    • Reactor containment vessel and nuclear power plant using it
    • 使用它的反应器容纳船和核电厂
    • JP2009150846A
    • 2009-07-09
    • JP2007330918
    • 2007-12-21
    • Toshiba Corp株式会社東芝
    • SATO TAKASHIOTONARI JUNICHIROFUJIKI YASUNOBUMIYAGAWA TAKUYASATO HISAKI
    • G21C9/004G21C13/00
    • G21C15/18G21C9/004G21C13/00G21Y2002/304G21Y2004/30Y02E30/32
    • PROBLEM TO BE SOLVED: To install a pressure suppression chamber in a large pressurized water reactor.
      SOLUTION: A reactor containment vessel for containing a reactor pressure vessel 2 storing a core 1 of the pressurized water reactor and a steam generator 3 includes a containment vessel body 7, a diaphragm partition 9 for separating the containment vessel body 7 into an upper vessel 10 and a lower vessel 11, the pressure suppression chamber 12 that has a pressure suppression pool 13 capable of storing water and whose gaseous phase section communicates with the upper vessel 10, and a LOCA vent pipe 15 for connecting the pressure suppression pool 13 to the lower vessel 11. An equipment such as the reactor pressure vessel 2 constituting a reactor coolant pressure boundary, or the steam generator 3, and a piping such as cold leg piping 4 or hot leg piping 5 are stored in the lower vessel 11.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:在大型压水反应堆中安装压力抑制室。 解决方案:用于容纳存储加压水反应堆的核心1的反应堆压力容器2和蒸汽发生器3的反应堆容纳容器包括容纳容器主体7,隔膜隔板9,用于将密封容器主体7分离成 上容器10和下容器11,具有能够储存水并且其气相部分与上容器10连通的压力抑制池13的压力抑制室12和用于连接压力抑制池13的LOCA排气管15 构成反应堆冷却剂压力边界的反应堆压力容器2或蒸汽发生器3以及诸如冷腿管4或热腿管5之类的管道的设备被储存在下部容器11中。 版权所有(C)2009,JPO&INPIT
    • 7. 发明专利
    • EMERGENCY CORE COOLING SYSTEM
    • JPH01207697A
    • 1989-08-21
    • JP3184888
    • 1988-02-16
    • TOSHIBA CORP
    • FUJIKI YASUNOBU
    • G21C9/004G21C9/00G21C15/18G21C19/30G21C19/307
    • PURPOSE:To decrease an operator's exposure by installing an insoluble impurity removing device to the outside of a pressure suppression pool. CONSTITUTION:A suction piping 25 is installed in the pressure suppression pool 4. This piping 25 is connected to a valve 26 installed on the outside of the pool 4. A strainer 29 which is the insoluble impurity removing device is installed between this valve 26 and an emergency core cooling pump 27 via a piping 28. The insoluble impurities in the pool 4 stick to the strainer 29 and the accumulation of the insoluble impurities in the cool 4 is prevented when a pump 27 is started. The insoluble impurities in the pool 4 stick to the strainer 29 and are thereby removed when a circulation operation is carried out by using a test line 20 and, therefore, the water quality of the pool 4 is improved. Further, the operator is capable of removing the strainer 29 and cleaning foreign matter therefrom without entering the pool 4, since the strainer 29 is installed on the outside of the pool 4. The operator's exposure is thereby decreased.
    • 9. 发明专利
    • Core melt holding structure
    • 核心熔体保持结构
    • JP2011232048A
    • 2011-11-17
    • JP2010100119
    • 2010-04-23
    • Toshiba Corp株式会社東芝
    • AOKI KAZUYOSHITAWARA MIKAOKUDA KENFUJIKI YASUNOBUSATO HISAKI
    • G21C9/016G21C5/10
    • G21C9/016Y02E30/40
    • PROBLEM TO BE SOLVED: To reduce the possibility that a reactor vessel is damaged by a high heat flux at a position where a metal layer is formed in the reactor vessel, when a reactor core melts down.SOLUTION: The reactor vessel 1 housing a reactor core includes: a lower-part support plate 6 having vertically passing through flow passage holes which are provided in the lower part of the reactor core and support the reactor core formed therein; a lower-part support plate supporter 7 which is fixed to the reactor vessel 1 and support the lower-part support plate 6; an insulating spacer 10; a net-like heat path 9 which is fixed to the lower-part support plate supporters 7 through the insulating spacer 10 and is brought into contact with the lower-part support plate 6; and a height-direction heat path 8 extending downwardly from the net-like heat path 9. The net-like heat path 9 and the height-direction heat path 8 have thermal conductivities higher than that of the insulating spacer 10.
    • 要解决的问题:为了减少在反应堆容器中形成金属层的位置处的反应堆容器被高热通量损坏的可能性,当反应堆堆芯熔化时。 解决方案:容纳反应堆堆芯的反应堆容器1包括:下部支撑板6,其具有垂直通过的流动通道孔,其设置在反应堆堆芯的下部并支撑形成在其中的反应堆芯; 下部支撑板支撑件7,其固定到反应堆容器1并支撑下部支撑板6; 绝缘垫片10; 网状热路9,其通过绝缘间隔件10固定到下部支撑板支撑体7并与下部支撑板6接触; 以及从网状热路9向下方延伸的高度方向热路8.网状热路9和高度方向热路8的导热率高于绝缘隔离物10的导热率。 (C)2012,JPO&INPIT
    • 10. 发明专利
    • Static cooling depressurization system and pressurized water nuclear power plant
    • 静态冷却减水系统和增压水核电厂
    • JP2009210283A
    • 2009-09-17
    • JP2008050873
    • 2008-02-29
    • Toshiba Corp株式会社東芝
    • SATO TAKASHIINO MASANORIFUJIKI YASUNOBUHASHIMOTO KAZUNORIOTONARI JUNICHIROSATO HISAKIMATSUNAGA NAOKO
    • G21C15/18
    • G21C9/004G21C1/086G21C15/18G21Y2002/304G21Y2004/30Y02E30/32
    • PROBLEM TO BE SOLVED: To reduce an influence exerted on an apparatus inside a reactor container, when a pressurized water reactor is cooled and shut down.
      SOLUTION: A static cooling depressurization system used for a pressurized water nuclear plant equipped with a reactor pressure vessel 2 for storing a core 1 cooled by a primary coolant, a pressurizer 80 for pressurizing a primary coolant pressure boundary wherein the primary coolant flows, and the reactor container for storing the reactor pressure vessel 2 and the pressurizer 80, is provided with a water tank 8 for internal fuel exchange used as a cooling water pool, a steam supply pipe 32 from a gas phase part where saturated steam 83 in the pressurizer 80 is positioned, a static RHR heat exchanger 61 for exchanging heat between water stored in the cooling water pool and steam flowing through the steam supply pipe 32, a steam supply valve 33 provided on the steam supply pipe 32, a coolant return pipe 65 extending from the static RHR heat exchanger 61 to a cold leg pipe 4 which is a liquid phase part of the primary coolant pressure boundary, and an outlet valve 64 provided on the coolant return pipe 65.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:为了减少对反应堆容器内的装置的影响,当压水反应堆被冷却和关闭时。 解决方案:一种用于加压水核电站的静态冷却减压系统,该加压水核电厂装备有用于存储由主冷却剂冷却的芯1的反应堆压力容器2,用于加压主冷却剂压力边界的加压器80,其中主冷却剂流动 和用于储存反应堆压力容器2和加压器80的反应容器设置有用作冷却水池的用于内部燃料更换的水箱8,来自气相部分的蒸汽供应管32,其中饱和蒸汽83在 定位加压器80,用于在存储在冷却水池中的水和通过蒸汽供给管32流动的蒸汽之间进行热交换的静态RHR热交换器61,设置在蒸汽供给管32上的蒸汽供给阀33,冷却剂返回管 65从静态RHR热交换器61延伸到作为主冷却剂压力边界的液相部分的冷腿管4,以及设置在该co olant返回管65.版权所有(C)2009,JPO&INPIT