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1. 发明授权

US06735267B2 Fuel assembly 失效
标题翻译：燃油组件
公开(公告)号：US06735267B2
公开(公告)日：2004-05-11
申请号：US10227441
申请日：2002-08-26
申请人： Akihito Orii , Junichi Koyama , Koji Nishida , Masao Chaki , Toru Kanazawa
发明人： Akihito Orii , Junichi Koyama , Koji Nishida , Masao Chaki , Toru Kanazawa
IPC分类号： G21C332
CPC分类号： G21C3/328 , G21Y2002/201 , G21Y2004/304 , Y02E30/38
摘要： A fuel assembly in accordance with the present invention comprises a plurality of first fuel rods and a plurality of second fuel rods having a length shorter than a length of the first fuel rod, and these two kinds of fuel rods are arranged in a fuel rod array of 10 rows by 10 columns. Two water rods are arranged in regions capable of arranging 8 fuel rods. The second fuel rods are not arranged in the outermost tier of the fuel rod array. Which satisfies the following conditions, that is, B≧60 (Equation 1) 15≦n≦20(n: integer) (Equation 2) Awr/Ach≦0.149 (Equation 3) Lp/Lf≧11/24 (Equation 4) Awr/Ach≧(3.00×10−4×n2+6.00×10−4×n−1.2×10−2)×(Lp/Lf−1)+1.75×10−1 (Equation 5) Awr/Ach≦(8.63×10−4×n2−6.09×10−2×n+1.33×10−1)×(Lp/Lf−8.32×10−1) (Equation 6) where Awr is a total sum of horizontal sectional areas of said water rods, Ach is a horizontal sectional area of a coolant flow passage in a bottom portion of said fuel assembly, Lf is an effective fuel length of said first fuel rod, n is number of said second fuel rods, Lp is an effective length of said second fuel rod, and B (GWd/t) is an average burn-up.
摘要翻译：根据本发明的燃料组件包括多个第一燃料棒和多个第二燃料棒，其长度短于第一燃料棒的长度，并且这两种燃料棒被布置在燃料棒阵列 10行×10列。在能够布置8个燃料棒的区域中布置两个水棒。第二燃料棒不配置在燃料棒阵列的最外层。其满足以下条件，即，Awr是所述水棒的水平截面积的总和，Ach是所述燃料组件的底部中的冷却剂流动通道的水平截面面积，Lf是有效燃料长度的所述第一燃料棒的数量，n是所述第二燃料棒的数量，Lp是所述第二燃料棒的有效长度，B（GWd / t）是平均燃耗。

2. 发明授权

US06516043B1 Fuel assembly and reactor core and fuel spacer and channel box 有权
标题翻译：燃油组件和反应堆核心和燃料间隔物和通道箱
公开(公告)号：US06516043B1
公开(公告)日：2003-02-04
申请号：US09471606
申请日：1999-12-23
申请人： Masao Chaki , Koji Nishida , Motoo Aoyama , Junichi Koyama , Katsumasa Haikawa , Yasuhiro Aizawa
发明人： Masao Chaki , Koji Nishida , Motoo Aoyama , Junichi Koyama , Katsumasa Haikawa , Yasuhiro Aizawa
IPC分类号： G21C300
CPC分类号： G21C3/324 , G21C3/328 , G21C3/332 , Y02E30/31 , Y02E30/38
摘要： A fuel assembly includes a plurality of fuel rods placed in a square lattice array of 9-rows/9-columns and at least one water rod. In this fuel assembly, the fuel rod pitch of the plurality of fuel rods is in a range of 14.15 mm to 14.65 mm, and means for offsetting and holding a fuel bundle composed of the fuel rods and the water rod is provided in such a manner that the center in a cross section of the fuel bundle is offset from the center in a cross section of the lower tie plate toward the channel fastener side. With this configuration, it is possible to provide a fuel assembly for a D-lattice core, which is capable of achieving the fuel economy comparable to that of a C-lattice core without reducing the thermal margin, and of using the existing fuel spacers.
摘要翻译：一种燃料组件包括多个放置在9列/ 9列的正方形格子阵列和至少一个水杆中的燃料棒。在该燃料组件中，多个燃料棒的燃料棒间距在14.15mm〜14.65mm的范围内，由燃料棒和水杆构成的燃料束的抵接和保持装置以这种方式燃料束的横截面中的中心在下连接板的横截面中朝向通道紧固件侧偏离中心。利用这种结构，可以提供一种用于D格子芯的燃料组件，其能够实现与C晶格铁芯的燃料经济性相当而不降低热裕度，并且使用现有的燃料间隔件。

3. 发明授权

US06337892B1 Boiling water reactor core, boiling water reactor, and method of operating boiling water reactor 有权
标题翻译：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。

4. 发明授权

US6141397A Boiling water reactor core, boiling water reactor, and method of operating boiling water reactor 有权
公开(公告)号：US6141397A
公开(公告)日：2000-10-31
申请号：US334624
申请日：1999-06-17
申请人： Masao Chaki , Koji Nishida
发明人： Masao Chaki , Koji Nishida
IPC分类号： G21C3/326 , G21C1/08 , G21C3/32 , G21C3/322 , G21C7/27 , G21C1/04
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.

5. 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。

6. 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。

7. 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℃。

8. 发明申请

US20070201604A1 STEAM SEPARATOR, BOILING WATER REACTOR AND SWIRLER ASSEMBLY 有权
标题翻译：蒸汽分离器，沸腾水反应器和SWIRLER总成
公开(公告)号：US20070201604A1
公开(公告)日：2007-08-30
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： G21C9/00
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二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。

9. 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。

10. 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℃。

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