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    • 3. 发明公开
    • NUCLEAR POWER PLANT AND REACTOR BUILDING GAS TREATMENT SYSTEM
    • KERNKRAFTANLAGE UNDREAKTORGEBÄUDEGASBEHANDLUNGSSYSTEM
    • EP2955719A2
    • 2015-12-16
    • EP15168908.0
    • 2015-05-22
    • Kabushiki Kaisha Toshiba
    • Sato, TakashiMatsumoto, Keiji
    • G21C9/004G21D1/02G21D3/06
    • G21C15/18G21C9/004Y02E30/40
    • A nuclear power plant according to an embodiment comprises: a reactor well (10); a reactor well upper lid (40); an operation floor (14); an operation floor area wall (14c); a standby gas treatment system (19); and a reactor well exhaust section (41) to release the gas inside the reactor well (10) to the environment without releasing the gas into the operation floor area (14a) in an event of a severe accident. The standby gas treatment system (19) includes: a suction pipe (20) to take in gas inside the reactor building (15); an exhaust fan (21); a standby gas treatment system exhaust pipe (23); a heater (60) that is disposed between the suction pipe (20) and the standby gas treatment system exhaust pipe (23); and a filter (22) to filter the gas heated by the heater (60) and to send the gas to the standby gas treatment system exhaust pipe (23).
    • 根据实施例的核电站包括:反应堆井(10); 反应器井盖(40); 操作台(14); 操作楼面壁(14c); 备用气体处理系统(19); 以及在严重事故的情况下将反应器井(10)内的气体释放到环境中而不将气体释放到操作底板区域(14a)中的反应堆井排出部分(41)。 备用气体处理系统(19)包括:吸入管(20),用于吸入反应堆建筑物内的气体; 排气风扇(21); 备用气体处理系统排气管(23); 设置在吸入管(20)和备用气体处理系统排气管(23)之间的加热器(60)。 以及过滤器(22),用于过滤由加热器(60)加热的气体并将气体送到备用气体处理系统排气管(23)。
    • 10. 发明公开
    • Nuclear power plant and passive containment cooling system
    • Kernkraftanlage和被动遏制Kühlsystem
    • EP2680272A2
    • 2014-01-01
    • EP13173429.5
    • 2013-06-24
    • Kabushiki Kaisha Toshiba
    • Sato, TakashiMatsumoto, Keiji
    • G21C15/18G21C9/004
    • G21C9/004G21C15/18Y02E30/40
    • According to an embodiment, a nuclear power plant has a core (1); a reactor pressure vessel (2); a dry well (4); a wet well (5); a vacuum breaker (9); a containment vessel (3) including the dry well (4), the LOCA vent pipe (8), the wet well (5), and the vacuum breaker (9); a cooling water pool (13) placed outside the containment vessel; a heat exchanger (16) at least partially submerged in cooling water (14); a gas supply pipe (20) connected to the inlet plenum (17) of the heat exchanger (16) and the dry well (4); a condensate return pipe (21) connected to the outlet plenum (18) of the heat exchanger (18) and the containment vessel (3); and a gas vent pipe (22) connected to the outlet plenum (18) of the heat exchanger (16) and an outside of the wet well (5) so that non-condensable gas inside the heat exchanger (16) is released out of the wet well (5). The gas vent pipe (22) is not connected to the wet well (5).
    • 根据实施例,核电站具有核心(1); 反应堆压力容器(2); 干井(4); 湿井(5); 真空断路器(9); 包括干井(4),LOCA排气管(8),湿井(5)和真空破坏器(9)的安全壳(3); 放置在安全壳外的冷却水池(13); 至少部分地浸没在冷却水(14)中的热交换器(16); 连接到热交换器(16)和干井(4)的入口增压室(17)的气体供应管(20); 连接到热交换器(18)和容纳容器(3)的出口增压室(18)的冷凝水回流管(21); 和连接到热交换器(16)的出口增压室(18)和湿井(5)的外部的排气管(22),使得热交换器(16)内的不可冷凝气体从 湿井(5)。 排气管(22)未连接到湿井(5)。