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    Reactor core
    1.
    发明授权
    Reactor core 有权
    反应堆核心

    公开(公告)号：US08064565B2

    公开(公告)日：2011-11-22

    申请号：US12624815

    申请日：2009-11-24

    申请人： Takeshi Mitsuyasu ,  Motoo Aoyama ,  Kazuya Ishii ,  Masao Chaki

    发明人： Takeshi Mitsuyasu ,  Motoo Aoyama ,  Kazuya Ishii ,  Masao Chaki

    IPC分类号： G21C23/00

    CPC分类号： G21C3/322 ,  G21C15/02 ,  G21Y2004/302 ,  Y02E30/38

    摘要： A reactor core, comprising: an outermost region; a core region surrounded by said outermost region; a plurality of fuel support members, each of which is disposed at a lower end portion of said outermost region and said core region; and a plurality of fuel assemblies loaded in said outermost region and said core region and supported by said fuel support members, wherein a plurality of fuel assemblies disposed in said core region include a plurality of first fuel assemblies, each of which is inserted into a first coolant passage which is formed in said fuel support member and has a first resistor having an opening, and a plurality of second fuel assemblies, each of which is individually inserted into each of second coolant passage which is formed in said fuel support member and has a second resistor having an opening and a larger pressure loss than that of said first resistor; and, four fuel assemblies, each of which is adjacent to each of four lateral sides of each of a plurality of first fuel assemblies, include either three or four second fuel assemblies.

    摘要翻译： 一种反应堆芯，包括：最外区; 由所述最外区域包围的芯区域; 多个燃料支撑构件，每个燃料支撑构件设置在所述最外区域的下端部分和所述芯区域; 以及多个燃料组件，其装载在所述最外区域和所述芯区域中并由所述燃料支撑构件支撑，其中设置在所述芯区域中的多个燃料组件包括多个第一燃料组件，每个第一燃料组件插入第一 冷却剂通道，其形成在所述燃料支撑构件中并且具有具有开口的第一电阻器，以及多个第二燃料组件，每个第二燃料组件分别插入形成在所述燃料支撑构件中的每个第二冷却剂通道中，并且具有 第二电阻器具有比所述第一电阻器的开口和更大的压力损失; 并且四个燃料组件中的每一个与多个第一燃料组件中的每一个的四个侧面中的每一个相邻，包括三个或四个第二燃料组件。

    Reactor Core
    2.
    发明申请
    Reactor Core 有权
    反应堆核心

    公开(公告)号：US20100128833A1

    公开(公告)日：2010-05-27

    申请号：US12624815

    申请日：2009-11-24

    申请人： Takeshi Mitsuyasu ,  Motoo Aoyama ,  Kazuya Ishii ,  Masao Chaki

    发明人： Takeshi Mitsuyasu ,  Motoo Aoyama ,  Kazuya Ishii ,  Masao Chaki

    IPC分类号： G21C15/00

    CPC分类号： G21C3/322 ,  G21C15/02 ,  G21Y2004/302 ,  Y02E30/38

    摘要： A reactor core, comprising: an outermost region; a core region surrounded by said outermost region; a plurality of fuel support members, each of which is disposed at a lower end portion of said outermost region and said core region; and a plurality of fuel assemblies loaded in said outermost region and said core region and supported by said fuel support members, wherein a plurality of fuel assemblies disposed in said core region include a plurality of first fuel assemblies, each of which is inserted into a first coolant passage which is formed in said fuel support member and has a first resistor having an opening, and a plurality of second fuel assemblies, each of which is individually inserted into each of second coolant passage which is formed in said fuel support member and has a second resistor having an opening and a larger pressure loss than that of said first resistor; and, four fuel assemblies, each of which is adjacent to each of four lateral sides of each of a plurality of first fuel assemblies, include either three or four second fuel assemblies.

    摘要翻译： 一种反应堆芯，包括：最外区; 由所述最外区域包围的芯区域; 多个燃料支撑构件，每个燃料支撑构件设置在所述最外区域的下端部分和所述芯区域; 以及多个燃料组件，其装载在所述最外区域和所述芯区域中并由所述燃料支撑构件支撑，其中设置在所述芯区域中的多个燃料组件包括多个第一燃料组件，每个第一燃料组件插入第一燃料组件 冷却剂通道，其形成在所述燃料支撑构件中并且具有具有开口的第一电阻器，以及多个第二燃料组件，每个第二燃料组件分别插入形成在所述燃料支撑构件中的每个第二冷却剂通道中，并且具有 第二电阻器具有比所述第一电阻器的开口和更大的压力损失; 并且四个燃料组件中的每一个与多个第一燃料组件中的每一个的四个侧面中的每一个相邻，包括三个或四个第二燃料组件。

    Boiling water reactor core, boiling water reactor, and method of operating boiling water reactor
    3.
    发明授权
    Boiling water reactor core, boiling water reactor, and method of operating boiling water reactor 有权
    沸水反应堆核心，沸水反应堆和沸水反应堆操作方法

    公开(公告)号：US06337892B1

    公开(公告)日：2002-01-08

    申请号：US09655882

    申请日：2000-09-06

    申请人： Masao Chaki ,  Koji Nishida

    发明人： Masao Chaki ,  Koji Nishida

    IPC分类号： G21C1502

    CPC分类号： G21C1/084 ,  G21C3/322 ,  G21Y2002/207 ,  G21Y2004/302 ,  Y02E30/31 ,  Y02E30/38

    摘要： In each of a number of fuel assemblies loaded in a core of a boiling water reactor, a fuel holding portion of a lower tie plate holds lower end portions a plurality of fuel rods and at least one water rod. The water rod includes a rising pipe opened to a space in the lower tie plate below the fuel holding portion and introducing upward a coolant introduced to the rising pipe, and a falling pipe communicated with the rising pipe and introducing downward the coolant introduced through the rising pipe. The falling pipe has a coolant outlet opened to a second coolant passage defined between the fuel rods above the fuel holding portion. The rising passage is filled with the coolant during a period of rated power operation of the reactor, and a surface of the coolant is formed in the rising pipe during a period of non-rated power operation in which a flow rate of the coolant supplied to the fuel assemblies is lower than that during the period of rated power operation. As a result, influences of a transient event during the rated power operation can be suppressed, and the nuclear thermal-hydraulic stability of the core during the non-rated power operation can be improved.

    摘要翻译： 在装载在沸水反应堆的核心中的多个燃料组件的每一个中，下连接板的燃料保持部分将下端部分保持多个燃料棒和至少一个水杆。 水杆包括向燃料保持部分下方的下连接板的空间开口的上升管，向上引入引入上升管的冷却剂，以及与上升管连通的下降管，向下引入通过上升引入的冷却剂 管。 下降管具有冷却剂出口，该冷却剂出口通向限定在燃料保持部分上方的燃料棒之间的第二冷却剂通道。 在反应堆的额定功率运行期间，上升通道充满冷却剂，并且在非额定功率运行期间，在上升管中形成冷却剂的表面，其中供应到 燃油组件比额定功率运转时低。 结果，可以抑制在额定功率运行期间的瞬态事件的影响，并且可以提高在非额定功率运行期间的核的核热液压稳定性。

    Steam separator, boiling water reactor and swirler assembly
    5.
    发明授权
    Steam separator, boiling water reactor and swirler assembly 有权
    蒸汽分离器，沸水反应器和旋流器组件

    公开(公告)号：US07835483B2

    公开(公告)日：2010-11-16

    申请号：US11679948

    申请日：2007-02-28

    申请人： Masao Chaki ,  Michio Murase ,  Naoyuki Ishida

    发明人： Masao Chaki ,  Michio Murase ,  Naoyuki Ishida

    IPC分类号： G21C15/00

    CPC分类号： G21C1/084 ,  B01D45/16 ,  B04C3/00 ,  B04C2003/006 ,  F22B37/327 ,  G21Y2002/201 ,  G21Y2004/302 ,  Y02E30/31

    摘要： A steam separator comprises an outer main swirler and an inner auxiliary swirler which is smaller than the main swirler. The swirlers are provided so as to be concentric on the inner wall at the lower side of the first stage inner cylinder. In the steam separator, when the gas-liquid two-phase flow which flows in the vicinity of the axial center of the first stage inner cylinder passes the auxiliary swirler, it is separated into steam and water by the centrifugal force. The separated water (droplets) is introduced into the main swirler. When the separated water (droplets) passes the main swirler, it is separated at the inner wall side of the first stage inner cylinder by the centrifugal force.Pressure loss in a steam separator is reduced and steam separation capability is increased without increasing the moisture from the steam separator.

    摘要翻译： 蒸汽分离器包括外主旋流器和小于主旋流器的内辅助旋流器。 旋流器设置成在第一级内筒的下侧的内壁上同心。 在蒸汽分离器中，当在第一级内筒的轴心附近流动的气液两相流通过辅助旋流器时，通过离心力将其分离成蒸汽和水。 分离的水（液滴）被引入主旋流器。 当分离的水（液滴）通过主旋流器时，其通过离心力在第一级内筒的内壁侧分离。 蒸汽分离器中的压力损失降低，并且蒸汽分离能力增加而不增加来自蒸汽分离器的水分。

    Nuclear power plant and operation method thereof
    8.
    发明申请
    Nuclear power plant and operation method thereof 有权
    核电厂及其运行方法

    公开(公告)号：US20050220253A1

    公开(公告)日：2005-10-06

    申请号：US11033953

    申请日：2005-01-13

    申请人： Kazuaki Kitou ,  Masao Chaki ,  Kouji Shina ,  Motoo Aoyama ,  Masaya Ohtsuka ,  Masayuki Nagasawa ,  Minoru Okura ,  Seiji Nemoto ,  Yasuhiro Takahashi

    发明人： Kazuaki Kitou ,  Masao Chaki ,  Kouji Shina ,  Motoo Aoyama ,  Masaya Ohtsuka ,  Masayuki Nagasawa ,  Minoru Okura ,  Seiji Nemoto ,  Yasuhiro Takahashi

    IPC分类号： G21C1/08 ,  G21C19/00 ,  G21D3/00

    CPC分类号： G21C1/08 ,  G21D3/00 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/39

    摘要： A nuclear power plant of the invention is equipped, for example, with a reactor; a steam loop comprising high and low pressure turbines; a condenser for condensing steam discharged therefrom the low pressure turbine; a feedwater heater for heating feedwater supplied from the condenser; and a feedwater loop for leading feedwater discharged from the feedwater heater to the reactor, and an operation method thereof is characterized by augmenting a second reactor thermal power output in a second operation cycle of the reactor larger than a first reactor thermal power output in a first operation cycle; and making an increase ratio of extraction steam, which is led to the feedwater heater with being extracted from the steam loop, in the second operation cycle for the first operation cycle smaller than an increase ratio of the second reactor thermal power output for the first reactor thermal power output.

    摘要翻译： 本发明的核电站例如配备有反应器; 包括高压和低压涡轮机的蒸汽回路; 用于冷凝从其排出的蒸汽的冷凝器; 用于加热从冷凝器供给的给水的给水加热器; 以及用于从给水加热器排放到反应器的引导给水的给水回路及其操作方法的特征在于，在反应器的第二操作循环中增加第二反应堆热功率输出，其大于第一反应堆热功率输出 操作周期; 并且在第一操作循环的第二操作循环中，使第一反应器的第二反应堆热功率输出的增加比率小于从蒸汽回路引出的给水加热器的提取比例增加 火力输出。

    Operation method of nuclear power plant
    10.
    发明授权
    Operation method of nuclear power plant 有权
    核电厂运行方式

    公开(公告)号：US08291704B2

    公开(公告)日：2012-10-23

    申请号：US13046329

    申请日：2011-03-11

    申请人： Masao Chaki ,  Kazuaki Kitou ,  Motoo Aoyama ,  Masaya Ootsuka ,  Kouji Shiina

    发明人： Masao Chaki ,  Kazuaki Kitou ,  Motoo Aoyama ,  Masaya Ootsuka ,  Kouji Shiina

    IPC分类号： G21D5/00 ,  F01K7/34

    CPC分类号： G21C1/084 ,  G21D1/02 ,  G21D3/00 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

    摘要： In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

    摘要翻译： 在核电站中，核反应堆的第二操作循环中的热功率在第二操作周期之前的第一操作周期内从热功率上升至少一个操作周期。 在蒸汽系统中提取的蒸汽的比例相对于主蒸汽的流量被引入特定从高压汽轮机的中间点和出口抽出的给水加热器在第二操作 循环，从而在第二操作循环中使得从给水加热器排出的给水温度降低1℃至40℃。