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    • 2. 发明授权
    • Reactor containment vessel
    • 反应堆安全壳
    • US5211906A
    • 1993-05-18
    • US615921
    • 1990-11-20
    • Shigeo HatamiyaMasanori NaitohYoshiyuki KataokaHiroaki SuzukiIsao SumidaToshitsugu NakaoKanehiro OchiaiTsuyoshi NiinoMasataka HidakaTohru FukuiRyuhei Kawabe
    • Shigeo HatamiyaMasanori NaitohYoshiyuki KataokaHiroaki SuzukiIsao SumidaToshitsugu NakaoKanehiro OchiaiTsuyoshi NiinoMasataka HidakaTohru FukuiRyuhei Kawabe
    • G21C13/00G21C15/18
    • G21C13/00G21C15/18Y02E30/40
    • A pressure control chamber of a reactor containment vessel for receiving the atmosphere of the reactor containment vessel containing leakage steam developing in the event of an accident includes a pressure control pool, and a wet well disposed above the pressure control pool. The wet well is divided into an inner peripheral portion and an outer peripheral portion. The inner and outer peripheral portions are communicated with each other via the pressure control pool. An outlet port for flowing the atmosphere of the reactor containment vessel containing the leakage steam is provided at the inner peripheral side of the pressure control pool. When the atmosphere of the reactor containment vessel containing the leakage steam is introduced into the pressure control pool in the event of the accident, this atmosphere is condensed by the water in the pressure control pool, and the gas of this atmosphere not condensed is accumulated in the inner peripheral portion of the wet well. As a result, the pressure within the inner peripheral portion is increased to increase the water level of the pressure control pool at the outer peripheral portion, so that the area of contact of a reactor containment vessel wall with the pressure control pool water is increased, thereby enhancing a heat radiation performance of the reactor containment vessel.
    • 用于接收包含在发生事故的情况下发生的泄漏蒸汽的反应堆容纳容器的气氛的反应堆容纳容器的压力控制室包括压力控制池和设置在压力控制池上方的湿井。 湿井分为内周部和外周部。 内外周部经由压力控制池相互连通。 在压力控制池的内周侧设置有用于使含有泄漏蒸汽的反应堆容纳容器的气流流出的出口。 当发生事故时,含有泄漏蒸汽的反应堆容纳容器的气氛被引入压力池中,该压力控制池中的水被浓缩,而且未浓缩的该气氛气体被积聚在 湿井的内周部分。 结果,增加了内周部分内的压力,以增加外周部分的压力控制池的水位,从而增加了反应堆容器壁与压力控制池水的接触面积, 从而提高反应堆容纳容器的散热性能。
    • 3. 发明授权
    • Reactor containment vessel
    • 反应堆安全壳
    • US5096659A
    • 1992-03-17
    • US436194
    • 1989-11-14
    • Masataka HidakaShigeo HatamiyaTerufumi KawasakiToru FukuiHiroaki SuzukiYoshiyuki KataokaRyuhei KawabeMichio MuraseMasanori Naitoh
    • Masataka HidakaShigeo HatamiyaTerufumi KawasakiToru FukuiHiroaki SuzukiYoshiyuki KataokaRyuhei KawabeMichio MuraseMasanori Naitoh
    • G21C9/004G21C15/18
    • G21C15/18Y02E30/40
    • A reactor containment vessel comprises typically a reactor pressure vessel housed in a dry well of the reactor containment vessel, a vent passage through which steam in the dry well is introduced into coolant accommodated in a pressure suppression chamber of the reactor containment vessel, a closed space formed at a position lower than the level of the normal liquid surface of the coolant, a first passage having an inlet opened into the pressure suppression chamber at a level higher than that of the normal liquid surface of the coolant and an outlet opened into the closed space, and a second passage communicating between the closed space and the dry well through a counter flow preventing arrangement for checking the flow directed toward the closed space, and therefore, noncondensable gas and liquid accumulated in the pressure suppression chamber are discharged into the dry well the pressure in which is higher than that in the pressure suppression chamber by making use of a difference in water head increased due to increase of the liquid while allowing fluid to be condensed to newly flow into the pressure suppression chamber from the dry well so as to be condensed, over a long cooling period after the occurrence of an accident of piping fracture in the reactor containment vessel. Owing to condensation, the pressure in the reactor containment vessel can be reduced, and moreover, fluid can make a natural circulation in a closed circuit passing through the dry well, the pressure suppression chamber and the closed space in order without flowing outside the circuit.
    • 反应堆容纳容器通常包括容纳在反应堆容纳容器的干燥井中的反应堆压力容器,将干井中的蒸汽引入容纳在反应堆容纳容器的压力抑制室中的冷却剂的通气通道,封闭空间 形成在低于冷却剂的正常液面的水平的位置处,具有以比冷却剂的通常液面高的水平方向通向压力抑制室的入口的第一通道和敞开的冷却剂出口 空间,以及第二通道,通过用于检查朝向封闭空间的流动的逆流防止装置在封闭空间和干井之间连通,因此积聚在压力抑制室中的不凝结气体和液体被排放到干井中 通过利用差i,其压力高于压力抑制室中的压力 n水头由于液体的增加而增加,同时允许流体冷凝,从干井中新流入压力抑制室,以便在发生管道破裂事故之后的长时间冷却期间冷凝 反应堆安全壳。 由于冷凝,可以减少反应堆容纳容器内的压力,而且,流体可以在通过干井,压力抑制室和封闭空间的闭路中自然循环,而不会流过电路外。
    • 8. 发明授权
    • Emergency core cooling system
    • 应急核心冷却系统
    • US4992231A
    • 1991-02-12
    • US587525
    • 1984-03-08
    • Yoshiyuki KataokaMasanori NaitohTakashi IkedaHisamichi InoueHiroaki Suzuki
    • Yoshiyuki KataokaMasanori NaitohTakashi IkedaHisamichi InoueHiroaki Suzuki
    • G21C15/18G21C9/012
    • G21C9/012Y02E30/40
    • An emergency core cooling system for spraying cooling water onto a nuclear reactor core of a nuclear reactor includes at least one header disposed in the nuclear reactor and arranged at an upper and outer circumferential position with respect to the reactor core. A plurality of spray nozzles are mounted on the at least one header for spraying cooling water onto the reactor core. The spray nozzles have a center axis and at least one of the plurality of spray nozzles is mounted on the at least one header so that the center axis thereof extends upwardly with respect to a horizontal axis whereas at least one of the remaining plurality of spray nozzles has the center axis thereof extending downwardly with respect to the horizontal axis. Cooling water is conducted to the at least one header for enabling spraying of the water in the emergency situation.
    • 用于将冷却水喷射到核反应堆的核反应堆核心上的应急芯冷却系统包括至少一个设置在核反应堆中并且相对于反应堆堆芯的上外周位置设置的集管。 多个喷嘴安装在至少一个集管上,用于将冷却水喷射到反应堆堆芯上。 喷嘴具有中心轴线,并且多个喷嘴中的至少一个安装在至少一个集管上,使得其中心轴线相对于水平轴线向上延伸,而剩余的多个喷嘴中的至少一个喷嘴 其中心轴线相对于水平轴线向下延伸。 冷却水被引导到至少一个头部,以便在紧急情况下喷洒水。