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公开(公告)号：US20100239061A1
公开(公告)日：2010-09-23
申请号：US12791379
申请日：2010-06-01
申请人： Kazuyoshi Aoki , Tomohisa Kurita , Toshimi Tobimatsu , Shinji Kubo , Mika Tahara , Ryoichi Hamazaki , Makoto Akinaga
发明人： Kazuyoshi Aoki , Tomohisa Kurita , Toshimi Tobimatsu , Shinji Kubo , Mika Tahara , Ryoichi Hamazaki , Makoto Akinaga
CPC分类号： G21C9/016 , G21C17/002 , G21C17/04 , Y02E30/40
摘要： A water leak detection floor transversally suspended by a pedestal side wall is installed between a reactor pressure vessel and a molten core holding apparatus. If a water leak occurs at the reactor pressure vessel, the water leak detection floor receives and detects the leak water. In a core meltdown accident, corium melts and penetrates the water leak detection floor and deposits on the molten core holding apparatus.
摘要翻译： 在反应堆压力容器和熔融铁芯保持装置之间安装由基座侧壁横向悬挂的漏水检测底板。 如果在反应堆压力容器发生漏水，则漏水检测底板接收并检测泄漏水。 在核心熔化事故中，ium熔融并渗透漏水检测地板并沉积在熔芯保持装置上。
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公开(公告)号：US20120328067A1
公开(公告)日：2012-12-27
申请号：US13478562
申请日：2012-05-23
申请人： Tomohisa KURITA , Mika Tahara , Mitsuo Komuro , Toshimi Tobimatsu , Ryo Suzuki , Ryoichi Hamazaki , Noriyuki Katagiri , Masashi Tanabe
发明人： Tomohisa KURITA , Mika Tahara , Mitsuo Komuro , Toshimi Tobimatsu , Ryo Suzuki , Ryoichi Hamazaki , Noriyuki Katagiri , Masashi Tanabe
摘要： An embodiment of a nuclear power plant has: a reactor vessel containing a core; a reactor containment vessel containing the reactor vessel; and a radiation heat reflecting member disposed at a portion below the reactor vessel inside the reactor containment vessel. The radiation heat reflecting member may block radiation heat, which is emitted toward a side wall surface of the reactor containment vessel from the core that has been put in a molten state by an accident and flowed downward from the reactor vessel to be accumulated at a lower portion of the reactor containment vessel. The radiation heat reflecting member may block radiation heat, which is emitted toward a supporting structure supporting devices disposed inside the reactor containment vessel.
摘要翻译： 核电站的一个实施例具有：包含核的反应堆容器; 容纳反应堆容器的反应堆容纳容器; 以及辐射热反射部件，设置在反应堆容纳容器内部的反应器容器下方的部分。 辐射热反射构件可以阻挡从反应堆容纳容器的侧壁表面发射的辐射热，该芯从已经被熔融状态的核心发生并且从反应堆容器向下流动以积聚在较低的 反应堆容器的一部分。 辐射热反射构件可以阻挡朝向设置在反应堆容纳容器内部的支撑结构支撑装置发射的辐射热。
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3.发明授权Core catcher, manufacturing method thereof, reactor containment vessel and manufacturing method thereof 有权核心捕手及其制造方法，反应堆安全壳及其制造方法公开(公告)号：US08358732B2
公开(公告)日：2013-01-22
申请号：US12195067
申请日：2008-08-20
申请人： Takashi Sato , Ryoichi Hamazaki , Mika Tahara , Yoshihiro Kojima , Hirohide Oikawa , Tomohisa Kurita , Seiichi Yokobori , Yuka Suzuki
发明人： Takashi Sato , Ryoichi Hamazaki , Mika Tahara , Yoshihiro Kojima , Hirohide Oikawa , Tomohisa Kurita , Seiichi Yokobori , Yuka Suzuki
IPC分类号： G21C9/00
CPC分类号： G21C9/016 , G21C21/00 , G21Y2002/201 , G21Y2004/30 , Y02E30/40
摘要： Core debris generated during a molten reactor core in a reactor containment vessel penetrating the reactor containment vessel is configured to be caught by a core catcher located beneath the reactor containment vessel which has a main body having first stage cooling water channels and second stage surrounded by cooling fins extending radially. The number of the second stage cooling channels is larger than that of the first stage cooling channels. Cooling water is supplied from a cooling water injection opening and distributed to the first cooling water channels at a distributor. An intermediate header is formed between the first and the second cooling water channels, and the cooling water is distributed to the second cooling water channels uniformly.
摘要翻译： 穿过反应堆容纳容器的反应堆容纳容器内的熔融反应堆核心期间产生的核心碎屑被构造成由位于反应堆容纳容器下方的芯捕获器捕获，该堆芯主体具有第一级冷却水通道，第二级由冷却 翅片沿径向延伸。 第二级冷却通道的数量大于第一级冷却通道的数量。 冷却水从冷却水注入口供给，并在分配器处分配到第一冷却水通道。 在第一和第二冷却水通道之间形成中间集管，并且冷却水均匀地分配到第二冷却水通道。
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4.发明申请REACTOR CONTAINMENT VESSEL COOLING SYSTEM, REACTOR CONTAINMENT VESSEL, AND REACTOR CONTAINMENT VESSEL COOLING METHOD 审中-公开反应器容器管冷却系统，反应器容器和反应器容器冷却方法公开(公告)号：US20110314858A1
公开(公告)日：2011-12-29
申请号：US13204000
申请日：2010-03-01
申请人： Mika Tahara , Mikihide Nakamaru , Akira Murase , Ryoichi Hamazaki
发明人： Mika Tahara , Mikihide Nakamaru , Akira Murase , Ryoichi Hamazaki
IPC分类号： F25D31/00
摘要： A reactor containment vessel cooling technology for preventing the cooling capability and structural integrity of a reactor containment vessel cooling system from decreasing by lowering the temperature of water vapor and gases acquired by the reactor containment vessel cooling system is provided. Based on the technology, the present invention provides a reactor containment vessel cooling system that acquires water vapor in a reactor containment vessel by using water vapor pressure in the vessel as a drive force, condenses the acquired water vapor into condensate, and cools the reactor containment vessel with the condensate. The reactor containment vessel cooling system includes a heat exchange pool 21 that is arranged apart from a dry well 15 and a suppression chamber 16 in the reactor containment vessel 10 and stores a medium for cooling water vapor, a heat exchanger 22 that is immersed in the heat exchange pool 21, acquires water vapor from the dry well 15 in the reactor containment vessel 10, and performs heat exchange between the eater vapor and the cooling medium in the heat exchange pool 21 to generate condensate, and a condensate drain pipe 25 that extracts the condensate from the heat exchanger 22 and guides and discharges the condensate toward a reactor pressure vessel 12.
摘要翻译： 提供一种用于防止反应堆容器冷却系统的冷却能力和结构完整性的反应堆容器冷却技术，其通过降低反应堆容器冷却系统获得的水蒸气和气体的温度而降低。 基于该技术，本发明提供了一种反应堆容器冷却系统，其通过使用容器中的水蒸汽压力作为驱动力来获取反应堆容器中的水蒸气，将获得的水蒸气冷凝成冷凝物，并冷却反应堆容器 容器与冷凝水。 反应堆安全壳冷却系统包括热交换池21，该热交换池21与反应堆容器10中的干井15和抑制室16分开设置，并储存用于冷却水蒸气的介质，将热交换器22浸入 热交换池21从反应堆容器10中的干井15获取水蒸气，并且在热交换池21中的蒸气与冷却介质之间进行热交换以产生冷凝物，并且提取冷凝水排出管25 来自热交换器22的冷凝物并将冷凝物引导并排出到反应堆压力容器12。
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公开(公告)号：US08537959B2
公开(公告)日：2013-09-17
申请号：US12821856
申请日：2010-06-23
IPC分类号： G21C9/00
摘要： A drain sump of a reactor containment vessel having a containment vessel floor down below a reactor pressure vessel, and includes a heat-proof sump cover and two or more drain flow paths. The drain sump is arranged inside the containment vessel floor. The heat-proof sump cover has a thickness, and covers an upper part of the drain sump. The thickness allows a top surface of the sump cover to lie in the same surface as a top surface of the containment vessel floor. The drain flow paths pass through the sump cover in a thickness direction to flow water therethrough and solidify a molten corium therein. The molten corium is produced in the unlikely event of a severe accident.
摘要翻译： 反应堆安装容器的排水槽，其具有位于反应堆压力容器下方的容纳容器底板，并且包括耐热贮槽盖和两个或更多个排水流路。 排水槽布置在安全壳底部。 耐热贮槽盖有一个厚度，并覆盖排水槽的上部。 该厚度允许贮槽盖的顶表面位于与容纳容器底板的顶表面相同的表面上。 排水流路在厚度方向上通过贮槽盖，使水流过其中，使其中的熔融的金属凝固。 在不太可能发生严重事故的情况下生产熔融的金属。
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公开(公告)号：US20100329409A1
公开(公告)日：2010-12-30
申请号：US12821856
申请日：2010-06-23
IPC分类号： G21C9/00
摘要： A drain sump of a reactor containment vessel having a containment vessel floor down below a reactor pressure vessel, and includes a heat-proof sump cover and two or more drain flow paths. The drain sump is arranged inside the containment vessel floor. The heat-proof sump cover has a thickness, and covers an upper part of the drain sump. The thickness allows a top surface of the sump cover to lie in the same surface as a top surface of the containment vessel floor. The drain flow paths pass through the sump cover in a thickness direction to flow water therethrough and solidify a molten corium therein. The molten corium is produced in the unlikely event of a severe accident.
摘要翻译： 反应堆安装容器的排水槽，其具有位于反应堆压力容器下方的容纳容器底板，并且包括耐热贮槽盖和两个或更多个排水流路。 排水槽布置在安全壳底部。 耐热贮槽盖有一个厚度，并覆盖排水槽的上部。 该厚度允许贮槽盖的顶表面位于与容纳容器底板的顶表面相同的表面上。 排水流路在厚度方向上通过贮槽盖，使水流过其中，使其中的熔融的金属凝固。 在不太可能发生严重事故的情况下生产熔融的金属。
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公开(公告)号：US09025721B2
公开(公告)日：2015-05-05
申请号：US13618641
申请日：2012-09-14
申请人： Kunihiko Wada , Fumiyo Kuno , Yutaka Ishiwata , Tsuneji Kameda , Ryoichi Hamazaki , Noriyuki Katagiri
发明人： Kunihiko Wada , Fumiyo Kuno , Yutaka Ishiwata , Tsuneji Kameda , Ryoichi Hamazaki , Noriyuki Katagiri
摘要： There is provided a holding device which can hold a molten corium for a predetermined period even when the molten corium is exposed to heat or undergoes any chemical reaction and which is applicable to practical use. There is provided a holding device provided below a nuclear reactor pressure vessel for holding a molten corium, wherein the holding device includes a base material in contact with a cooling medium, and a multilayer stack structure on the base material. The multilayer stack structure has a first layer having heat-resistant property, a second layer formed on the first layer and having heat-resistant property with lower heat conductivity than that of the first layer, and a third layer formed on the second layer and having corrosion-resistant property and impact-absorbing property.
摘要翻译： 提供了一种保持装置，即使在熔融的金属暴露于热或经历任何化学反应并且适用于实际应用的情况下，其也可以将熔融的金属晶体保持预定的时间。 提供了一种保持装置，其设置在用于保持熔融的金属的核反应堆压力容器下方，其中保持装置包括与冷却介质接触的基材，以及在基材上的多层堆叠结构。 多层堆叠结构具有耐热性的第一层，形成在第一层上的具有比第一层低的导热性的耐热性的第二层，以及形成在第二层上的第三层，具有 耐腐蚀性和冲击吸收性。
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公开(公告)号：US20130070886A1
公开(公告)日：2013-03-21
申请号：US13618641
申请日：2012-09-14
申请人： Kunihiko WADA , Fumiyo Kuno , Yutaka Ishiwata , Tsuneji Kameda , Ryoichi Hamazaki , Noriyuki Katagiri
发明人： Kunihiko WADA , Fumiyo Kuno , Yutaka Ishiwata , Tsuneji Kameda , Ryoichi Hamazaki , Noriyuki Katagiri
IPC分类号： G21C9/016
摘要： There is provided a holding device which can hold a molten corium for a predetermined period even when the molten corium is exposed to heat or undergoes any chemical reaction and which is applicable to practical use. There is provided a holding device provided below a nuclear reactor pressure vessel for holding a molten corium, wherein the holding device includes a base material in contact with a cooling medium, and a multilayer stack structure on the base material. The multilayer stack structure has a first layer having heat-resistant property, a second layer formed on the first layer and having heat-resistant property with lower heat conductivity than that of the first layer, and a third layer formed on the second layer and having corrosion-resistant property and impact-absorbing property.
摘要翻译： 提供了一种保持装置，即使在熔融的金属暴露于热或经历任何化学反应并且适用于实际应用的情况下，其也可以将熔融的金属晶体保持预定的时间。 提供了一种保持装置，其设置在用于保持熔融的金属的核反应堆压力容器下方，其中保持装置包括与冷却介质接触的基材，以及在基材上的多层堆叠结构。 多层堆叠结构具有耐热性的第一层，形成在第一层上的具有比第一层低的导热性的耐热性的第二层，以及形成在第二层上的第三层，具有 耐腐蚀性和冲击吸收性。
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