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1. 发明授权

US08064565B2 Reactor core 有权
标题翻译：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。

2. 发明申请

US20100128833A1 Reactor Core 有权
标题翻译：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。

3. 发明申请

US20080317191A1 OPERATING METHOD OF NUCLEAR REACTOR AND NUCLEAR POWER GENERATION PLANT 审中-公开
标题翻译：核反应堆和核发电厂的运行方法
公开(公告)号：US20080317191A1
公开(公告)日：2008-12-25
申请号：US11765486
申请日：2007-06-20
申请人： Masao Chaki , Motoo Aoyama , Tetsushi Hino , Kazuya Ishii
发明人： Masao Chaki , Motoo Aoyama , Tetsushi Hino , Kazuya Ishii
IPC分类号： G21C7/32
CPC分类号： G21C7/32 , G21D3/14 , Y02E30/39
摘要： The present invention decreases the temperature of feed water supplied to the reactor of a set power when the flow rate of coolant supplied to the core of the reactor increases in the end of an operation cycle. This operating method can increase the thermal power of the nuclear power generation plant and increase the economical efficiency of fuel even when the operation cycle is prolonged. Particularly, even when the core flow rate increases in the end of the operation cycle, this method can suppress the rise of the cooling water temperature at the inlet of the core. Consequently, this invention can make the reactivity gain higher than that when the core flow rate is singly increased.The present invention can increase the thermal power of a nuclear reactor, and can improve the economical efficiency of fuel even when a period of an operation cycle is made longer.
摘要翻译：本发明在供给到反应堆的核心的冷却剂的流量在操作循环结束时增加时，将供给反应器的供给水的温度降低到设定功率。这种操作方法可以增加核发电厂的热功率，并且即使在延长操作周期时也可提高燃料的经济效率。特别是即使在运转循环结束时核心流量增加的情况下，也能够抑制芯体入口处的冷却水温度升高。因此，本发明可以使反应性增益高于芯流量单独增加时的反应性增益。本发明可以增加核反应堆的热功率，并且即使在使操作周期更长的时间内也能提高燃料的经济性。

4. 发明授权

US07997078B2 Operation method of nuclear power plant 有权
标题翻译：核电厂运行方式
公开(公告)号：US07997078B2
公开(公告)日：2011-08-16
申请号：US12574219
申请日：2009-10-06
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℃。

5. 发明申请

US20070000250A1 Operation method of nuclear power plant 有权
标题翻译：核电厂运行方式
公开(公告)号：US20070000250A1
公开(公告)日：2007-01-04
申请号：US11340643
申请日：2006-01-27
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
CPC分类号： G21C1/084 , G21D1/02 , G21D3/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： A nuclear power plant and an operation method of the nuclear power plant, which can uprate plant power without greatly modifying the construction of plant equipment, while keeping a core's pressure loss characteristic, a safety margin, and a design margin in the transient state substantially the same as those before the power uprate. 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 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 temperature of feedwater discharged from the feedwater heater lowers in the range of 1° C. to 40° C. in the second operation cycle.
摘要翻译：一个核电站和核电厂的运行方式，可以在不大幅度修改工厂设备的情况下，提高设备功率，同时保持核心的压力损失特性，安全裕量和瞬态状态下的设计余量与上电前相同。核反应堆的第二操作循环中的热功率在第二操作循环之前的第一操作循环中从热功率升高至少一个操作周期。在第二操作循环中，相对于主蒸汽的流量，从蒸汽系统提取并被引入特定从高压涡轮的中间点和出口抽出的给水加热器的一部分蒸汽减少从第一操作循环中的过程中，使得从给水加热器排出的给水温度在第二操作循环中在1℃至40℃的范围内降低。

6. 发明授权

US08291704B2 Operation method of nuclear power plant 有权
标题翻译：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℃。

7. 发明申请

US20110162364A1 OPERATION METHOD OF NUCLEAR POWER PLANT 有权
公开(公告)号：US20110162364A1
公开(公告)日：2011-07-07
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 , F01K23/02
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.

8. 发明授权

US07614233B2 Operation method of nuclear power plant 有权
标题翻译：核电厂运行方式
公开(公告)号：US07614233B2
公开(公告)日：2009-11-10
申请号：US11340643
申请日：2006-01-27
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
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℃。

9. 发明授权

US06205196B1 Boiling water type nuclear reactor core and operation method thereof 失效
标题翻译：沸水型核反应堆堆芯及其运行方法
公开(公告)号：US06205196B1
公开(公告)日：2001-03-20
申请号：US09048994
申请日：1998-03-27
申请人： Junichi Yamashita , Kumiaki Moriya , Katsumasa Haikawa , Yasuhiro Masuhara , Taichi Takii , Akihiro Yamanaka , Takao Kondo , Motoo Aoyama , Masao Chaki
发明人： Junichi Yamashita , Kumiaki Moriya , Katsumasa Haikawa , Yasuhiro Masuhara , Taichi Takii , Akihiro Yamanaka , Takao Kondo , Motoo Aoyama , Masao Chaki
IPC分类号： G21C334
CPC分类号： G21C7/113 , Y02E30/31 , Y02E30/39
摘要： A boiling water type nuclear reactor core, in which a plurality of fuel assemblies, each enclosed in a channel box, are loaded and a plurality of control rods, each having control blades, are arranged between the channel boxes. Latitudinal long blade control rods, each having control rod blades which extend latitudinally in four directions, are arranged between channel boxes on diagonals of square bundle regions each formed by a plurality of fuel assemblies, and latitudinal short blade control rods, each having control rod blades which extend latitudinally in four directions with each control rod blade having a latitudinal length of about half of the width of one of the square bundle regions, are arranged between the channel boxes in the center of each of the square bundle regions. The long blade control rods have a latitudinal blade length which is about twice as long as the latitudinal blade length of the short blade control rods.
摘要翻译：沸水型核反应堆核心，其中装有封闭在通道箱中的多个燃料组件，并且在通道箱之间设置有多个控制杆，每个控制杆具有控制叶片。横向长叶片控制棒，每个具有沿四个方向纬向延伸的控制杆叶片，布置在每个由多个燃料组件形成的方形束区域的对角线上的通道箱和纬向短叶片控制棒之间，每个具有控制杆叶片每个方形束区域的中心处的通道箱之间布置有横截面在四个方向上的横截面，每个控制杆叶片具有约一个平方束区域的宽度的大约一半的纬度长度。长叶片控制杆具有纬度叶片长度，其长度为短叶片控制棒的纬向叶片长度的两倍。

10. 发明授权

US08453451B2 Operation method of nuclear power plant 有权
公开(公告)号：US08453451B2
公开(公告)日：2013-06-04
申请号：US13046294
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
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.

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