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    • 1. 发明专利
    • Emergency core cooling system
    • 应急核心冷却系统
    • JP2005201742A
    • 2005-07-28
    • JP2004007349
    • 2004-01-14
    • Toshiba Corp株式会社東芝
    • SATO TAKASHIOIKAWA HIROHIDE
    • G21C9/00G21C15/18G21D3/04
    • G21C15/18Y02E30/31
    • PROBLEM TO BE SOLVED: To provide an optimum emergency core cooling system for next generation BWR plants by responding to the necessity of a proper design which has arisen in the emergency core cooling system in an ABWR and by reducing more the cost effects and arrangement effects.
      SOLUTION: The emergency core cooling system which is constituted of two safety categories of active emergency core cooling system having one high-pressure core cooling system and one low-pressure core cooling system shared with a residual heat removal system is provided.
      COPYRIGHT: (C)2005,JPO&NCIPI
    • 要解决的问题:通过响应ABWR中的应急核心冷却系统中出现的正确设计的必要性,并通过减少成本效应和更多的成本效应,为下一代BWR设备提供最佳应急核心冷却系统, 安排效果。

      解决方案:提供由两个安全类别的主动应急核心冷却系统组成的应急核心冷却系统,其具有一个高压核心冷却系统和一个与残余散热系统共用的低压核心冷却系统。 版权所有(C)2005,JPO&NCIPI

    • 5. 发明专利
    • Molten corium cooling device, reactor containment vessel, and installation method of molten corium cooling device
    • 冷凝器冷却装置,反应器容器,以及冷却装置的安装方法
    • JP2007232529A
    • 2007-09-13
    • JP2006053660
    • 2006-02-28
    • Toshiba Corp株式会社東芝
    • HAMAZAKI RYOICHITAWARA MIKAKOJIMA YOSHIHIROOIKAWA HIROHIDE
    • G21C9/016
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To improve cooling efficiency of molten corium generated when the core in a reactor vessel melts and penetrates the reactor vessel without enlarging the floor area. SOLUTION: The under side of the reactor vessel includes a molten corium cooling device 30 having a water supply chamber 10, a plurality of water channels 11 having a lower inlet section 21 connected to this and an upper outlet section 22 opened upward, and a heat resistant material 12 attached to the top surfaces of the water channels 11. The plurality of water channels 11 are combined so as to form a circular conical shape opening upward. Cooling water is supplied to the water supply chamber 10 via a water injection pipe 8. The cooling water is distributed to the water channels 11 by the water supply chamber 10, goes up in a cooling water channel 25 with tilting, overflows from the upper outlet section 22, and cools the molten corium 13 deposited on the heat resistant material 12. The overflowing water passes a circulation pipe 9, and is returned to the water supply chamber 10. COPYRIGHT: (C)2007,JPO&INPIT
    • 要解决的问题:为了提高当反应堆容器中的芯熔化并渗透反应堆容器而产生的熔融的金属的冷却效率而不扩大地板面积。 解决方案:反应器容器的下侧包括具有供水室10的熔融ium冷却装置30,具有与其连接的下入口部21和向上开口的上出口部22的多个水通道11, 以及安装在水通道11的顶面上的耐热材料12.多个水通道11组合形成向上开口的圆锥形状。 冷却水经由注水管8供给到供水室10.冷却水由供水室10分配到水通道11,在倾斜的冷却水通道25中上升,从上部出口溢出 部分22,冷却沉积在耐热材料12上的熔融的金属13。溢流水通过循环管9,并返回到供水室10.版权所有(C)2007,JPO&INPIT
    • 6. 发明专利
    • Method and device for removing hydrogen in reactor containment vessel
    • 用于在反应器容器中移除氢的方法和装置
    • JP2005003371A
    • 2005-01-06
    • JP2003163582
    • 2003-06-09
    • Toshiba Corp株式会社東芝
    • MURAKAMI KAZUOICHIKAWA NAGAYOSHIARAI KENJIOIKAWA HIROHIDEHAMAZAKI RYOICHI
    • G21C9/04G21C9/00G21D3/08
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a method and a device for removing hydrogen in a reactor containment vessel which can restrain the internal pressure of the reactor containment vessel from rising due to hydrogen by allowing a catalyst for reacting hydrogen with nitrogen to deliver its original performance to effectively remove hydrogen.
      SOLUTION: The device has a structure equipped with a cabinet which is placed in the reactor containment vessel and has openings in its upper and lower parts, a hydrogen/oxygen catalyst which is placed closer to the lower opening of the cabinet to form water from oxygen and hydrogen and a hydrogen/nitrogen catalyst which is placed above the hydrogen/oxygen catalyst to produce ammonia from nitrogen and hydrogen.
      COPYRIGHT: (C)2005,JPO&NCIPI
    • 解决的问题:提供一种用于除去反应堆容纳容器中的氢气的方法和装置,其可以通过允许氢气与氮气反应的催化剂来输送,从而可以抑制反应堆容器的内部压力由于氢而升高 其原有性能有效去除氢气。 解决方案:该装置具有装配有柜体的结构,其被放置在反应堆容纳容器中并且在其上部和下部具有开口,氢/氧催化剂被放置成更靠近柜的下部开口形成 来自氧和氢的水和氢/氮催化剂,其置于氢/氧催化剂上方以产生来自氮和氢的氨。 版权所有(C)2005,JPO&NCIPI
    • 7. 发明专利
    • Device and method for protecting reactor pressure vessel
    • 用于保护反应器压力容器的装置和方法
    • JP2004233259A
    • 2004-08-19
    • JP2003024171
    • 2003-01-31
    • Toshiba Corp株式会社東芝
    • SHIRAKAWA NORIYUKIHORIE HIDEKINAKAHARA KATSUHIKOOIKAWA HIROHIDE
    • G21C9/016G21C13/00
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To provide a device for protecting a reactor pressure vessel which can efficiently cool molten debris that has dropped to the bottom of the reactor pressure vessel. SOLUTION: In the device for protecting the reactor pressure vessel which is placed at the bottom of it to hold the molten debris generated in case of the meltdown of a core, a layer of a low-melting metal whose melting point is lower than that of the molten debris is located at the bottom of the reactor pressure vessel. As for the layer of the low-melting metal, lumps of low-melting metals may be arranged. It is acceptable that the layer of the low-melting metal has layers where lumps of low-melting metals are arranged. The layer of the low-melting metal may consist of a container made of a low-melting metal located at the bottom of the reactor pressure vessel and the powder of the low-melting metal filling the container made of the low-melting metal. COPYRIGHT: (C)2004,JPO&NCIPI
    • 要解决的问题:提供一种用于保护反应堆压力容器的装置,其可以有效地冷却已经滴落到反应堆压力容器底部的熔融碎屑。 解决方案:在用于保护放置在其底部的反应堆压力容器的装置中,以保持在芯部熔化的情况下产生的熔融碎屑,熔点较低的低熔点金属层 比熔融碎屑的位置位于反应堆压力容器的底部。 对于低熔点金属的层,可以布置低熔点金属块。 可以接受的是,低熔点金属层具有布置低熔点金属块的层。 低熔点金属层可以由位于反应堆压力容器底部的低熔点金属容器和填充由低熔点金属制成的容器的低熔点金属的粉末组成。 版权所有(C)2004,JPO&NCIPI
    • 8. 发明专利
    • COOLING FACILITY OF NUCLEAR POWER PLANT
    • JPH04136794A
    • 1992-05-11
    • JP25694590
    • 1990-09-28
    • TOSHIBA CORP
    • OIKAWA HIROHIDE
    • G21C15/18
    • PURPOSE:To make possible the removal of decay heat generated in a reactor core by providing an emergency condenser housed in a cooling water source, primary piping connecting the emergency condenser to the gas phase part of a reactor pressure vessel and secondary piping coupling the emergency condenser to the reactor pressure vessel. CONSTITUTION:A nuclear power plant is provided with a reactor pressure vessel 21, a reactor containment vessel 22 and the like. The steam generated by the decay heat of a reactor core is led into an emergency condenser 32 through primary piping 31 from the reactor pressure vessel 21 to cool to condense in heat-transfer tubes to become condensed water to return to the reactor pressure vessel 21 through secondary piping 34, latent heat which the steam has is transmitted to the cooling water source on the outside of the reactor containment vessel 22 through the heat-transfer tubes of an emergency condenser 32, and non-condensable gas allowed to flow in the emergency condenser 32 leads part of the steam produced in the reactor core to the downstream side of the emergency condenser 32 so as to exhaust into a suppression chamber from tertiary piping 36.
    • 10. 发明专利
    • EMERGENCY CORE COOLING SYSTEM FOR NUCLEAR REACTOR
    • JPH1130685A
    • 1999-02-02
    • JP18615297
    • 1997-07-11
    • TOSHIBA CORP
    • SATO TAKASHIOIKAWA HIROHIDEOSHIMA KOICHIROMUTA HITOSHISHIOIRI AKIOFUJIKI YASUNOBUUSUI HIDEKAZU
    • G21C15/18G21D3/04
    • PROBLEM TO BE SOLVED: To further heighten reliability of nuclear power installations by operating an emergency core cooling system without depending on a power supply in a plant at the time of LOCA(loss of coolant accident). SOLUTION: A generator 21 driven by a gas turbine 22 is provided as a tail machine of an emergency diesel generator 6 supplying electricity to a lubricating water pump 13 provided at water filling piping 15 of a high pressure core water filling system of an ECCS, an auxiliary machine cooling system 19, and the like, and a changeover machine 23 is provided to change over a power source from a D/G 6 to the gas turbine generator 21. In the case of the failure of the D/G 6 and in the case of being unable to use electric power inside and outside of an electric power plant at the time of LOCA, power is supplied to various equipment of the high pressure core water filling system from the gas turbine generator 21 by the changeover machine 23. There are a method of providing container spray piping branching off from the water filling piping 15 and a method of providing the auxiliary machine cooling system 19 with a cooling device that can be switched over to a sea water cooling system 30. A section to which such a high pressure core water filling system belongs is divided from other electrically and physically independent sections.