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    • 1. 发明专利
    • Emergency core cooling system
    • 应急核心冷却系统
    • JP2009031079A
    • 2009-02-12
    • JP2007194220
    • 2007-07-26
    • Toshiba Corp株式会社東芝
    • YAMAZAKI KOUJISUZUKI YUKASHIMIZU TAKEO
    • G21C15/18G21C9/00
    • G21C15/18G21C15/182G21Y2002/304G21Y2002/50G21Y2004/304Y02E30/31
    • PROBLEM TO BE SOLVED: To provide an emergency core cooling system wherein an injection system has redundancy so as to inject the reactor coolant into a reactor pressure vessel even when single failure occurs on another emergency power, and two divisions out of three divisions of the emergency core cooling systems can not be used, and furthermore, when rupture occurs on a part of a connection piping in one usable division of the emergency core cooling system while performing on-line maintenance of the emergency power of an arbitrary system.
      SOLUTION: An emergency core cooling system 1 includes: three systems of low-pressure injection system 19 having a low-pressure injection pump 18 for electric drive; three systems of high-pressure core injection system 22 having a high-pressure core injection pump 21 for electric drive; and an automatic pressure reducing system 26.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:提供一种应急芯冷却系统,其中注射系统具有冗余性,以便即使在另一应急电源发生单次故障时也将反应堆冷却剂注入反应堆压力容器中,并且三个部门中的两个部分 的应急核心冷却系统不能使用,此外,当在任意系统的应急电力进行在线维护时,在应急核心冷却系统的一个可用部分中的连接管道的一部分发生破裂。 解决方案:应急芯冷却系统1包括:具有用于电驱动的低压喷射泵18的三个低压喷射系统19系统; 具有用于电力驱动的高压铁心注射泵21的高压铁心注射系统22的三个系统; 和自动减压系统26.版权所有(C)2009,JPO&INPIT
    • 2. 发明专利
    • COOLANT CLEANING SYSTEM FOR NUCLEAR REACTOR
    • JPH03170095A
    • 1991-07-23
    • JP30766289
    • 1989-11-29
    • TOSHIBA CORP
    • SHIMIZU TAKEOFUJIKI YASUNOBU
    • G21C19/307
    • PURPOSE:To shorten the inspection and maintenance (shutdown) period of a residual heat removing system and to improve the working rate of a power plant by providing stop valves for the circulation of a reactor coolant and cooling water, respectively, between plural units of non-regeneration heat exchangers which are connected in series. CONSTITUTION:The system constitution similar to the system constitution of the conventional reactor coolant 2 is obtd. when the non-regeneration heat exchangers 6a and 6b, 6c and 6d are connected in series to each other. The reactor coolant is circulated at the rate sufficient for cleaning the coolant during the operation of a reactor 2 and the function to clean the reactor coolant is, therefore, exhibited if a non-heat exchange valve 9 is opened. On the other hand, the non-regeneration heat exchangers 6a and 6b, 6c and 6d are connected in parallel to each other at the time of inspection and maintenance of the reactor 2. The flow rates of the reactor coolant and the cooling water increase to twice the flow rates of the conventional system. The heat removing capacity of about 1.5 times the heat removing capacity of the conventional reactor coolant cleaning system is, therefore, obtd. in the reactor coolant cleaning system 20.
    • 6. 发明专利
    • Leakage water collector, nuclear power plant and leakage monitoring method
    • 泄漏水收集器,核电厂和泄漏监测方法
    • JP2010237070A
    • 2010-10-21
    • JP2009086030
    • 2009-03-31
    • Toshiba Corp株式会社東芝
    • SHIMIZU TAKEOTAWARA MIKAARIMA YUKIHAMAZAKI RYOICHIMIYAGAWA TAKUYA
    • G21C9/016G21C17/02G21D1/00
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To reduce risks on the breakdown of a core catcher due to a delay in water injection in case of a core damage accident and those on steam explosion in case of a drop of a molten core.
      SOLUTION: A nuclear power plant includes a corium holding vessel 62 which is placed below a reactor vessel 1 inside a containment vessel 2 and opens upward, structures such as pedestal walls 14 forming a cooling flow channel 50 extending along outside faces to exit below the rim of the opening of the vessel, feedwater piping 12 for supplying cooling water to the cooling flow channel 50, feedwater valves 8 mounted on the feedwater piping 12, and a drain accumulation lid 5 for covering the opening. The use of the cooling flow channel 50 as a drain waste liquid sump brings the full-time existence of the cooling water in the cooling flow channel 50.
      COPYRIGHT: (C)2011,JPO&INPIT
    • 要解决的问题:为了减少由于核心损坏事故造成的注水延迟引起的核心捕集器故障的风险,以及在熔融芯的下降时蒸汽爆炸的风险。 解决方案:核电站包括一个放置在容器2内的反应容器1的下面并向上开放的ium保持容器62,诸如底座壁14的结构形成一个沿着外表面延伸的冷却流道50 在容器的开口的边缘下方,用于向冷却流路50供给冷却水的给水管道12,安装在给水管12上的给水阀8,以及用于覆盖开口的排水积存盖5。 使用冷却流路50作为排水废液池,在冷却流路50中全部存在冷却水。版权所有(C)2011,JPO&INPIT