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1. 发明申请

US20100329409A1 DRAIN SUMP OF NUCLEAR REACTOR CONTAINMENT VESSEL 失效
标题翻译：核反应堆容器船的排水管
公开(公告)号：US20100329409A1
公开(公告)日：2010-12-30
申请号：US12821856
申请日：2010-06-23
申请人： Makoto AKINAGA , Hiromasa Yanagisawa , Hirohide Oikawa , Ryoichi Hamazaki
发明人： Makoto AKINAGA , Hiromasa Yanagisawa , Hirohide Oikawa , Ryoichi Hamazaki
IPC分类号： G21C9/00
CPC分类号： G21C9/016 , G21C15/02 , G21C15/18 , Y02E30/40
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。

2. 发明申请

US20090080589A1 CORE CATCHER, MANUFACTURING METHOD THEREOF, REACTOR CONTAINMENT VESSEL AND MANUFACTURING METHOD THEREOF 有权
标题翻译：核心捕获器及其制造方法，反应器容器及其制造方法
公开(公告)号：US20090080589A1
公开(公告)日：2009-03-26
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： G21C9/016
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。

3. 发明授权

US08537959B2 Drain sump of nuclear reactor containment vessel 失效
标题翻译：核反应堆安全壳排水槽
公开(公告)号：US08537959B2
公开(公告)日：2013-09-17
申请号：US12821856
申请日：2010-06-23
申请人： Makoto Akinaga , Hiromasa Yanagisawa , Hirohide Oikawa , Ryoichi Hamazaki
发明人： Makoto Akinaga , Hiromasa Yanagisawa , Hirohide Oikawa , Ryoichi Hamazaki
IPC分类号： G21C9/00
CPC分类号： G21C9/016 , G21C15/02 , G21C15/18 , Y02E30/40
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。

4. 发明授权

US07983376B2 Boiling water nuclear reactor and emergency core cooling system of the same 有权
标题翻译：沸水核反应堆和应急核心冷却系统相同
公开(公告)号：US07983376B2
公开(公告)日：2011-07-19
申请号：US12828798
申请日：2010-07-01
申请人： Yoshihiro Kojima , Takashi Sato , Hirohide Oikawa
发明人： Yoshihiro Kojima , Takashi Sato , Hirohide Oikawa
IPC分类号： G21C9/00
CPC分类号： G21C15/18 , G21C9/004 , Y02E30/31
摘要： A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool.
摘要翻译：沸水核反应堆包括：包括干井和湿井的反应堆安全壳; 连通干井和压力池的排气管; 用重力驱动的注水池来保持硼酸水溶液; 用于使重力驱动注水池中的硼酸水溶液落下以便在反应堆事故发生时被注入反应堆压力容器的应急核心注水管道系统; 静态容器冷却系统池; 静态容器冷却系统热交换器; 连接静电容器冷却系统热交换器的上部和干井的干井连接管; 以及用于将静电容器冷却系统热交换器中的不可冷凝气体排放到压力抑制池的内部的排气管。

5. 发明申请

US20110158371A1 PRESSURIZED WATER REACTOR PLANT 有权
标题翻译：加压水反应堆厂
公开(公告)号：US20110158371A1
公开(公告)日：2011-06-30
申请号：US13044909
申请日：2011-03-10
申请人： Takashi SATO , Kazunori Hashimoto , Hirohide Oikawa , Yasunobu Fujiki , Makoto Akinaga , Hisaki Sato
发明人： Takashi SATO , Kazunori Hashimoto , Hirohide Oikawa , Yasunobu Fujiki , Makoto Akinaga , Hisaki Sato
IPC分类号： G21C17/00 , G21C9/004 , G21C9/00
CPC分类号： G21C1/086 , G21C9/004 , G21C15/18 , Y02E30/32
摘要： According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.
摘要翻译：根据实施例，压水反应堆设备具有主要系统，其包括：用于容纳由主冷却剂冷却的反应堆堆芯的反应堆容器，单个蒸汽发生器，用于连接反应堆容器的热腿管和蒸汽发电机，冷腿管，至少两个一次冷却剂泵，以及用于对初级冷却剂流动的主冷却剂压力边界加压的加压器。该设备还具有：被动冷却和减压系统，其是在蒸汽发生器的管道破裂事故发生时使初级系统压力与二次系统压力相等的主要减压装置，以及包含主系统的反应堆安全壳并通过空气冷却冷却主系统。因此，可以提供具有高经济性，安全性和可靠性的紧凑型压水机。

6. 发明授权

US08817941B2 Pressurized water reactor plant 有权
标题翻译：加压水反应堆厂
公开(公告)号：US08817941B2
公开(公告)日：2014-08-26
申请号：US13044909
申请日：2011-03-10
申请人： Takashi Sato , Kazunori Hashimoto , Hirohide Oikawa , Yasunobu Fujiki , Makoto Akinaga , Hisaki Sato
发明人： Takashi Sato , Kazunori Hashimoto , Hirohide Oikawa , Yasunobu Fujiki , Makoto Akinaga , Hisaki Sato
IPC分类号： G21C9/004 , G21C15/18 , G21C9/00 , G21C15/00
CPC分类号： G21C1/086 , G21C9/004 , G21C15/18 , Y02E30/32
摘要： According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.
摘要翻译：根据实施例，压水反应堆设备具有主要系统，其包括：用于容纳由主冷却剂冷却的反应堆堆芯的反应堆容器，单个蒸汽发生器，用于连接反应堆容器的热腿管和蒸汽发电机，冷腿管，至少两个一次冷却剂泵，以及用于对初级冷却剂流动的主冷却剂压力边界加压的加压器。该设备还具有：被动冷却和减压系统，其是在蒸汽发生器的管道破裂事故发生时使初级系统压力与二次系统压力相等的主要减压装置，以及包含主系统的反应堆安全壳并通过空气冷却冷却主系统。因此，可以提供具有高经济性，安全性和可靠性的紧凑型压水机。

7. 发明授权

US07835482B2 Emergency core cooling system 有权
标题翻译：应急核心冷却系统
公开(公告)号：US07835482B2
公开(公告)日：2010-11-16
申请号：US11033272
申请日：2005-01-12
申请人： Takashi Sato , Hirohide Oikawa
发明人： Takashi Sato , Hirohide Oikawa
IPC分类号： G21C9/00
CPC分类号： G21C15/18 , Y02E30/31
摘要： An emergency core cooling system comprises first and second safety divisions for an active emergency core cooling system. Each of the first and second safety divisions is provided with a high-pressure core cooling system and a low-pressure core cooling system, which also acts as a residual heat removal system.
摘要翻译：应急核心冷却系统包括用于主动应急核心冷却系统的第一和第二安全部门。第一和第二安全部分中的每一个都设置有高压芯冷却系统和低压芯冷却系统，其还用作残余散热系统。

8. 发明授权

US08358732B2 Core catcher, manufacturing method thereof, reactor containment vessel and manufacturing method thereof 有权
标题翻译：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。

9. 发明申请

US20090060112A1 BOILING WATER NUCLEAR REACTOR AND EMERGENCY CORE COOLING SYSTEM OF THE SAME 审中-公开
标题翻译：锅炉水核反应堆及其应急核心冷却系统
公开(公告)号：US20090060112A1
公开(公告)日：2009-03-05
申请号：US12056813
申请日：2008-03-27
申请人： Yoshihiro KOJIMA , Takashi Sato , Hirohide Oikawa
发明人： Yoshihiro KOJIMA , Takashi Sato , Hirohide Oikawa
IPC分类号： G21C9/004 , G21C9/00
CPC分类号： G21C15/18 , G21C9/004 , Y02E30/31
摘要： A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool.
摘要翻译：沸水核反应堆包括：包括干井和湿井的反应堆安全壳; 连通干井和压力池的排气管; 用重力驱动的注水池来保持硼酸水溶液; 用于使重力驱动注水池中的硼酸水溶液落下以便在反应堆事故发生时被注入反应堆压力容器的应急核心注水管道系统; 静态容器冷却系统池; 静态容器冷却系统热交换器; 连接静电容器冷却系统热交换器的上部和干井的干井连接管; 以及用于将静电容器冷却系统热交换器中的不可冷凝气体排放到压力抑制池的内部的排气管。

10. 发明授权

US5149492A Reactor containment vessel 失效
标题翻译：反应堆安全壳
公开(公告)号：US5149492A
公开(公告)日：1992-09-22
申请号：US732237
申请日：1991-07-18
申请人： Kenji Arai , Hirohide Oikawa , Hideo Nagasaka
发明人： Kenji Arai , Hirohide Oikawa , Hideo Nagasaka
IPC分类号： G21C9/004 , G21C15/18
CPC分类号： G21C15/18 , Y02E30/40
摘要： A reactor containment vessel with a cooling system includes a communication pipe having a valve to be connected to either an emergency condenser or suppression chamber in order to improve cooling performance by removing non-condensable gas from heat exchanger tubes when a main steam line is broken. One open end of the communication pipe is opened and positioned at a low position of the dry well. The valve is constantly closed and actuated to be opened in an abnormal condition of a reactor. When the valve is opened, the communication pipe introduces the non-condensable gas existing in the emergency condenser or suppression chamber to the low area of the dry well due to a density differential between steam and non-condensable gas, thus removing the non-condensable gas from the heat exchanger tubes, and improving the cooling performance of the emergency condenser.
摘要翻译：具有冷却系统的反应堆容纳容器包括连接管，该连通管具有连接到应急冷凝器或抑制室的阀，以便当主蒸汽管线断裂时通过从热交换器管去除不可冷凝气体来改善冷却性能。连通管的一个开口端打开并定位在干井的低位置。阀门经常关闭并致动以在反应堆的异常状态下打开。当阀打开时，由于蒸汽和不可冷凝气体之间的密度差，连通管将存在于紧急冷凝器或抑制室中的不可冷凝气体引入干井的低区域，从而去除不可冷凝来自热交换器管的气体，以及提高应急冷凝器的冷却性能。

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