公开(公告)号：EP2757339A4

公开(公告)日：2015-08-26

申请号：EP12831668

申请日：2012-09-13

申请人： HISAKA WORKS LTD ,  HITACHI GE NUCLEAR ENERGY LTD

发明人： HIWATASHI ISAMU ,  IWAKI MANA ,  KUSUNOKI KENJI ,  MATSUMURA SEIICHI ,  ISHIHAMA KIYOSHI ,  FUNABIKI TAKAHISA

IPC分类号： F28F3/10 ,  F28D9/00 ,  F28D9/02 ,  F28F3/08

CPC分类号： F28F3/10 ,  F28D9/005 ,  F28F3/083 ,  F28F9/0251 ,  F28F2230/00 ,  F28F2265/06 ,  F28F2265/16 ,  F28F2265/22

摘要： To provide a plate heat exchanger free from degradation of gaskets which form a flow path through which a high-temperature fluid flows. In the plate heat exchanger, a plurality of heat transfer plates 20 each provided with passage holes 21, 22, 23, and 24 in corners are stacked; a flow-path forming gasket 31 is interposed between peripheries of each adjacent ones of the heat transfer plates 20; communicating-path forming gaskets 32 are installed, surrounding the passage holes 21 in each adjacent ones of the heat transfer plates 20 alternately; and thereby a first flow path 1 adapted to pass a high-temperature fluid H, a second flow path adapted to pass a low-temperature fluid C, and communicating paths 3 adapted to cause the high-temperature fluid H and the low-temperature fluid C, respectively, to flow in and out of the first flow path 1 and the second flow path 2 are formed alternately on opposite sides of each of the heat transfer plates 20. The flow-path forming gasket 31 is made up of an inner gasket member 31a and an outer gasket member 31b arranged in two parallel lines.

公开(公告)号：EP2355106B1

公开(公告)日：2014-10-15

申请号：EP11000361.3

申请日：2011-01-18

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Narita, Shintaro ,  Osaka, Masaaki

IPC分类号： G21C13/02 ,  G21C13/08 ,  E04B2/86 ,  F16J12/00

CPC分类号： G21C13/02 ,  G21C13/08 ,  H01L2924/1301 ,  Y02E30/40 ,  H01L2924/00

公开(公告)号：EP2772718A1

公开(公告)日：2014-09-03

申请号：EP12843569.0

申请日：2012-10-23

申请人： Hisaka Works, Ltd. ,  Hitachi-GE Nuclear Energy, Ltd.

发明人： HIWATASHI, Isamu ,  IWAKI, Mana ,  KUSUNOKI, Kenji ,  ISHIHAMA, Kiyoshi ,  MATSUMURA, Seiichi ,  FUNABIKI, Takahisa

IPC分类号： F28F3/10 ,  F28F3/04 ,  F28F3/08 ,  F28F11/00

CPC分类号： F28D9/0062 ,  F28D9/005 ,  F28F3/042 ,  F28F3/08 ,  F28F3/083 ,  F28F3/10 ,  F28F2275/205

摘要： Heat transfer plates are stacked, each being provided with a plurality of passage holes, a flow-path forming gasket is interposed between peripheries of each adjacent ones of the heat transfer plates, thereby alternately forming a first flow path to pass a high-temperature fluid, a second fluid to pass a low-temperature fluid, and communicating paths to cause the fluids to flow in and out of the first flow path and the second flow path on opposite sides of each heat transfer plate, and communicating-path forming gaskets surrounding the passage holes are interposed between adjacent ones of the heat transfer plates, thereby forming a communicating path to cause a fluid to flow in and out of the first flow path and a communicating path to cause a fluid to flow in and out the second flow path. Each communicating-path forming gasket is made up of inner and outer gasket members arranged in two lines, the inner gasket member surrounding the passage holes while the outer gasket member surrounding the inner gasket member.

摘要翻译： 传热板被层叠，每个传热板设置有多个通道孔，流动通道形成垫片被插入在每个相邻的传热板的外围之间，从而交替地形成第一流动通道以通过高温流体 ，使低温流体通过的第二流体和使流体流入和流出位于每个传热板的相对侧上的第一流动路径和第二流动路径的连通路径以及围绕周围的连通路径形成垫圈 通路孔介于相邻的传热板之间，由此形成使流体流入和流出第一流路和连通路的连通路，以使流体流入和流出第二流路 。 每个连通路径形成垫片由布置成两行的内部和外部垫圈构件组成，内部垫圈构件围绕通道孔，而外部垫圈构件围绕内部垫圈构件。

公开(公告)号：EP2767653A2

公开(公告)日：2014-08-20

申请号：EP14153885.0

申请日：2014-02-04

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Miyajima, Ayumu ,  Ishigaki, Hirokuni ,  Onitsuka, Shohei ,  Tanaka, Hidenori

IPC分类号： E04H9/02 ,  E04B1/98

摘要： Higher-order vibration is controlled in an event that an impact load such as an aircraft impact is applied to a nuclear plant.
A higher-order vibration control device 1 is installed in a nuclear plant having a reactor containment vessel and a nuclear reactor building 3. The higher-order vibration control device 1 includes an impactor 1a, a housing 1b which receives the reaction force of the impactor 1a, and a locking mechanism 2. The impactor 1a is installed on a floor 31 of the nuclear plant so as to roll in a horizontal direction with respect to the floor 31. The housing 1b encloses the impactor 1a and guides rolling of the impactor 1a. The locking mechanism 2 restrains rolling of the impactor 1a. In the event that a flying object may possibly impact the nuclear plant, the locking of the locking mechanism 2 is released.

摘要翻译： 在对核电站施加诸如飞机冲击的冲击载荷的情况下，控制高阶振动。 高级振动控制装置1安装在具有反应堆安装容器和核反应堆3的核电站中。高级振动控制装置1包括冲击器1a，容纳冲击器的反作用力的壳体1b 1a和锁定机构2.冲击器1a安装在核电站的地板31上，以相对于地板31在水平方向上滚动。壳体1b包围冲击器1a并引导冲击器1a的滚动 。 锁定机构2限制冲击器1a的滚动。 在飞行物体可能会影响核电站的情况下，释放锁定机构2的锁定。

公开(公告)号：EP2725582A1

公开(公告)日：2014-04-30

申请号：EP13189648.2

申请日：2013-10-22

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Ikegawa, Tomohiko ,  Kito, Kazuaki

IPC分类号： G21C9/012 ,  G21C15/18

CPC分类号： G21C15/18 ,  G21C9/012 ,  Y02E30/40

摘要： Disclosed is a passive residual heat removal system and nuclear power plant equipment configured to alleviate a rise in an internal pressure of a primary containment vessel (17), even if fluid line breakage of a reactor pressure vessel (15) occurs and for whatever reason, supply of a coolant (2) to the reactor pressure vessel (15) fails.
This invention includes: a heat exchanger (1) provided at a position higher than a primary containment vessel (17); a condensate storage tank (5) disposed below the heat exchanger and above an upper end of a reactor core (13) placed in a reactor pressure vessel (15); a non-condensate gas discharge line (8) connected at a first end thereof to an upper section of the condensate storage tank (5) and at a second end thereof to a suppression pool (20); a second condensate discharge line (9) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the non-condensate gas discharge line (8) is connected, and at a second end thereof to the suppression pool (20); and a condensate return line (10) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the second condensate discharge line (9) is connected, and at a second end thereof to a side portion of the reactor pressure vessel (15), the side portion being above the upper end of the core (13).

摘要翻译： 公开了一种被动的残余散热系统和核动力装置设备，其构造成即使发生反应堆压力容器（15）的流体管线断裂，并且由于任何原因，减轻主要容纳容器（17）的内部压力的升高， 向反应堆压力容器（15）供应冷却剂（2）失败。 本发明包括：设置在高于主要容纳容器（17）的位置处的热交换器（1）; 设置在所述热交换器的下方和放置在反应堆压力容器（15）内的反应堆芯（13）的上端上方的冷凝水储存箱（5）。 一个非冷凝气体排放管线（8），其第一端连接到冷凝水储存箱（5）的上部，第二端连接到一个抑制池（20）; 第二冷凝物排出管线（9），其在其第一端连接到所述冷凝水罐（5）的所述非冷凝气体排出管线（8）的第一端所连接的所述部分下方的位置，并且在 第二端到达抑制池（20）; 以及冷凝水返回管线（10），其在其第一端连接到第二冷凝物排出管线（9）的第一端连接到的冷凝水储存罐（5）的该部分下方的位置，并且在第二端 在所述反应堆压力容器（15）的侧部，所述侧部位于所述芯（13）的上端之上。

公开(公告)号：EP2177904B1

公开(公告)日：2013-05-08

申请号：EP09012979.2

申请日：2009-10-14

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Aoike, Satoru ,  Tanaka, Masaaki ,  Kurosawa, Koichi

IPC分类号： G01N29/00 ,  G21C17/003 ,  B29C39/00 ,  B08B3/12

CPC分类号： G21C17/003

公开(公告)号：EP2549484A1

公开(公告)日：2013-01-23

申请号：EP12175231.5

申请日：2012-07-06

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Kito, Kazuaki ,  Matsuura, Masayoshi ,  Ando, Koji

IPC分类号： G21C15/18

CPC分类号： G21C9/004 ,  G21C15/18 ,  G21C15/182 ,  Y02E30/40

摘要： A nuclear power plant has a reactor pressure vessel (1), a primary containment vessel (3) and a passive pressure suppression pool cooling system. The reactor pressure vessel (1) is installed in the primary containment vessel (3). A pressure suppression pool (7) filled with cooling water is formed in a lower portion of the primary containment vessel (3). The passive pressure suppression pool cooling system is provided with a steam condensing pool (5) in which cooling water is filled, disposed outside the primary containment vessel (3), a steam condenser (4) disposed in the steam condensing pool (5), a steam supply pipe (2) connecting the reactor pressure vessel (1) to the steam condenser (4), and a condensed water discharge pipe (6) connected to the steam condenser (4) for discharging condensed water generated in the steam condenser (4). Another end portion of the condensed water discharge pipe (6) is disposed in the pressure suppression pool (7).

摘要翻译： 一个核电厂有反应堆压力容器（1），初级容纳容器（3）和被动压力抑制池冷却系统。 反应堆压力容器（1）安装在初级容纳容器（3）中。 在主要容纳容器（3）的下部形成有填充有冷却水的压力池（7）。 被动压力抑制池冷却系统设置有一个蒸汽冷凝池（5），其中装有冷却水，设置在初级容纳容器（3）的外部，设置在蒸汽冷凝池（5）中的蒸汽冷凝器（4） 将反应堆压力容器（1）连接到蒸汽冷凝器（4）的蒸汽供应管（2）和连接到蒸汽冷凝器（4）的冷凝水排出管（6），用于排出在蒸汽冷凝器中产生的冷凝水 4）。 冷凝水排出管（6）的另一端部设置在压力抑制池（7）中。

公开(公告)号：EP2525218A1

公开(公告)日：2012-11-21

申请号：EP12168471.6

申请日：2012-05-18

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Baba, Atsushi ,  Musha, Yoshinori ,  Koike, Masahiro

IPC分类号： G01N29/22 ,  G01N29/24

CPC分类号： G01N29/228 ,  G01N29/245 ,  G01N2291/0289 ,  Y10T29/42

摘要： A heat-resistant ultrasonic sensor forms a piezo-electric ceramics film 3 with a thickness of 0.5 mm or smaller and a Curie point of 200°C or higher on a flexible metal plate 2. A thin metal film that is an electrode 4 is attached to a top surface of the piezo-electric ceramics film and a metal wire mesh 5 covers the thin metal film 4 and is attached to a top surface of the thin metal film 4. A core of a heat-resistant coaxial cable 7 is connected to the metal wire mesh at a connection point. The heat-resistant coaxial cable 7 is fixed to the thin metal plate 2 with a metal fixing member 8 that is a ground portion. An electric insulating cover 10 is attached to the thin metal plate 2 and covers the piezo-electric ceramics film 3, the thin metal film 4, the metal wire mesh 5, the connection point 6, the fixing member 8, and the core 9 of the coaxial cable 7. A defect of a structural member of a plant can be accurately detected by the heat-resistant ultrasonic sensor when the plant is in operation.

摘要翻译： 耐热超声波传感器在柔性金属板2上形成厚度为0.5mm以下，居里点为200℃以上的压电陶瓷膜3.附着有作为电极4的金属薄膜 到压电陶瓷膜的顶面，金属丝网5覆盖薄金属膜4，并附着在金属薄膜4的上表面。耐热同轴电缆7的芯与 金属丝网在连接点处。 耐热同轴电缆7用作为接地部的金属固定部件8固定在金属薄板2上。 电绝缘盖10安装在薄金属板2上，并且覆盖压电陶瓷膜3，金属薄膜4，金属丝网5，连接点6，固定件8和芯9的压电陶瓷膜3 同轴电缆7.当工厂运行时，可以由耐热超声波传感器精确地检测出设备的结构部件的缺陷。

公开(公告)号：EP2518731A2

公开(公告)日：2012-10-31

申请号：EP12165594.8

申请日：2012-04-26

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Namba, Koji ,  Ohtsuka, Masaya ,  Fujimura, Koji

IPC分类号： G21C9/004 ,  G21C15/18 ,  G21C19/07 ,  G21D3/06

CPC分类号： G21C19/07 ,  G21C9/004 ,  G21D3/06 ,  Y02E30/40

摘要： A nuclear power plant and a fuel pool water cooling facility and method are provided that can suppress the decrease of a water level in a fuel pool with no power supply at the time of malfunction of a circulating water system.
The nuclear power plant includes a reactor pressure vessel 2 that encompasses a reactor 1 containing nuclear fuel; a containment vessel 3 for housing the reactor pressure vessel 2; a fuel pool 11 for storing spent fuel 12; a reactor building 10 that houses the reactor pressure vessel 2, the containment vessel 3 and the fuel pool 11; a circulating water system 21 adapted to forced-circulating-cool the fuel pool water 14 in the fuel pool 11; and at least one heat pipe 13 for transferring heat of the fuel pool water 14 in the fuel pool 11 and discharging the heat to the atmosphere.

摘要翻译： 提供一种核电站和燃料池水冷却设备和方法，其能够抑制在循环水系统发生故障时没有电源的燃料池中的水位的下降。 核电厂包括反应堆压力容器2，其包含含有核燃料的反应器1; 用于容纳反应堆压力容器2的容纳容器3; 用于储存乏燃料12的燃料池11; 容纳反应堆压力容器2的反应堆10，容纳容器3和燃料池11; 适于强制循环冷却燃料池11中的燃料池水14的循环水系统21; 以及至少一个热管13，用于将燃料池11中的燃料池水14的热传递到燃料池11中，并将热量排放到大气中。

公开(公告)号：EP2177904A3

公开(公告)日：2012-02-29

申请号：EP09012979.2

申请日：2009-10-14

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Aoike, Satoru ,  Tanaka, Masaaki ,  Kurosawa, Koichi

IPC分类号： G01N29/00 ,  G21C17/003 ,  B29C39/00 ,  B08B3/12

CPC分类号： G21C17/003

摘要： In an underwater remote surface inspection method for a reactor constituting member, in order to improve the precision of an operation of inspecting a surface shape of the reactor constituting member, an underwater remote surface inspection apparatus (1) includes a replica picking head (7), an ultrasonic vibrator (11), and a replica agent cartridge (20). The replica picking head (7) is pressed against a surface of core internal structure (40) as an inspection target. A replica agent is supplied from the replica agent cartridge (20) into the replica agent supply region (38) formed inside the replica picking head (7) and contacting with the surface of the core internal structure (40). After the operation of supplying the replica agent ends, an ultrasonic wave (39) is transmitted from an ultrasonic vibrator (11) to the replica agent inside the replica agent supply region (38). Accordingly, gas bubbles or liquid bubbles existing inside the replica agent supply region (38) rise up so as to be discharged to the outside of the replica picking head (7) through an air extracting hole (8). As a result, the gas bubbles or the liquid bubbles do not remain in the surface of the replica agent contacting with the surface of the core internal structure (40).