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    • 4. 发明申请
    • Boiling water reactor nuclear power plant
    • 沸水堆核电站
    • US20020101951A1
    • 2002-08-01
    • US09978304
    • 2001-10-17
    • Mikihide NakamaruHideaki HekiTakehiko SaitoKouji HiraiwaTadashi NarabayashiSatoru OomizuTsuyoshi ShimodaKenji AraiShinichi MorookaSeijiro Suzuki
    • G21C009/00
    • G21C15/18G21C1/084G21C9/004Y02E30/31
    • The present invention provides a boiling water-type nuclear power plant comprising: a passive safety system having depressurization valves and a gravity driven core cooling system as an emergency core cooling system; a passive containment vessel cooling system in which reactor steam released in the containment vessel is cooled by a heat exchanger in a cooling water pool installed in the upper portion of the containment vessel; and a containment vessel flooding system which injects cooling water into a dry well of the containment vessel on an accident; wherein a containment vessel spray cooling system for injecting cooling water into the containment vessel via a pump is further added as a safety system. According to the above configuration, it becomes possible to achieve reliable depressurization by an active safety system of the containment vessel on the basis of a simplified passive safety system, and to depressurize the containment vessel and limit radioactive leakage over extended periods after an accident.
    • 本发明提供了一种沸水型核电站,包括:具有减压阀的无源安全系统和作为应急芯冷却系统的重力驱动核心冷却系统; 被动容纳容器冷却系统,其中在容纳容器中释放的反应器蒸汽由安装在安全壳上部的冷却水池中的热交换器冷却; 以及在事故中将冷却水注入安全壳的干井内的遏制船只淹水系统; 其特征在于,进一步添加用于将冷却水经由泵将冷却水喷射到所述容纳容器内的收容容器喷雾冷却系统作为安全系统。 根据上述结构,能够以简化的被动安全系统为基础,通过安全壳的主动安全系统实现可靠的减压,并且能够在事故发生后的长时间内使密闭容器减压并限制放射性泄漏。
    • 9. 发明申请
    • Reactor cooling system
    • 反应堆冷却系统
    • US20040196947A1
    • 2004-10-07
    • US10387372
    • 2003-03-14
    • Toshimitsu UsuiKoji AndoMasayoshi Matsuura
    • G21C009/00
    • G21C15/00G21C15/24Y02E30/40
    • The present invention is characterized by a reactor cooling system, which comprises a lower drywell which is a space for containing a bottom side portion of the reactor pressure vessel, the lower drywell being disposed in a lower portion of the reactor pressure vessel; reactor recirculation pumps for circulating cooling water in the reactor pressure vessel, the reactor recirculation pump being disposed in the bottom side portion of the reactor pressure vessel in such a manner that a side of a motor portion of the reactor recirculation pump is projected into the lower drywell; and heat exchangers disposed in the lower drywell, the cooling water circulated by the reactor recirculation pump passing through the heat exchanger, wherein number of the reactor recirculation pumps is 4 or 6, and the reactor recirculation pumps are arranged with nearly equal angular spacing.
    • 本发明的特征在于反应器冷却系统,其包括下部干井,其是用于容纳反应堆压力容器底部的空间,下部干井设置在反应堆压力容器的下部; 用于在反应堆压力容器中循环冷却水的反应器再循环泵,反应堆再循环泵以这样的方式设置在反应堆压力容器的底侧部分,使得反应堆再循环泵的马达部分的一侧投影到下部 干井 以及设置在下部干井中的热交换器,由反应器再循环泵循环通过热交换器的冷却水,其中反应器再循环泵的数量为4或6,并且反应器再循环泵以几乎相等的角度间隔排列。