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1. 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。

2. 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。

3. 发明授权

US06510192B1 Boiling water type nuclear reactor core and operation method thereof 有权
标题翻译：沸水型核反应堆堆芯及其运行方法
公开(公告)号：US06510192B1
公开(公告)日：2003-01-21
申请号：US09703933
申请日：2000-11-02
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. Long blade control rods, each having control rod blades which extend in four directions, are arranged between channel boxes on diagonals of square bundle regions each formed by a plurality of fuel assemblies, and short blade control rods, each having a control rod blade 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.
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。每个具有四个方向延伸的控制杆叶片的长叶片控制棒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之间，以及短叶片控制棒，每个叶片控制棒的控制杆叶片长度其中一个平方束区域的宽度的大约一半被布置在每个平方束区域的中心的通道盒之间。

4. 发明授权

US6005905A Initial core 失效
标题翻译：初始核心
公开(公告)号：US6005905A
公开(公告)日：1999-12-21
申请号：US664663
申请日：1996-06-17
申请人： Akihiro Yamanaka , Katsumasa Haikawa , Akiko Kanda , Takaaki Mochida , Junichi Yamashita , Motoo Aoyama , Yoko Yuchi , Junichi Koyama
发明人： Akihiro Yamanaka , Katsumasa Haikawa , Akiko Kanda , Takaaki Mochida , Junichi Yamashita , Motoo Aoyama , Yoko Yuchi , Junichi Koyama
IPC分类号： G21C3/30 , G21C3/326 , G21C3/328 , G21C3/62 , G21C5/00 , G21C7/02 , G21C19/00
CPC分类号： G21C5/00 , G21C7/02 , G21Y2002/201 , G21Y2004/30 , G21Y2004/402 , Y02E30/39
摘要： In an arrangement of an initial core, the core is loaded with 572 high enrichment fuel assemblies H with 4.2 wt % average enrichment and 300 low enrichment fuel assemblies L with 1.5 wt % average enrichment. The average enrichment of the core is about 3.3 wt %. In this core, only the low enrichment fuel assemblies are loaded into the most outer position of the core and the high enrichment fuel assemblies are loaded into an area other than the most outer position. In this arrangement, the average enrichment of reload fuel assemblies is 3.7 wt %.
摘要翻译：在初始核心的布置中，核心装载有572个高浓缩燃料组件H，4.2重量％的平均浓缩物和300个低富集燃料组件L，具有1.5重量％的平均富集度。核心的平均富集度约为3.3重量％。在该核心中，只有低浓度燃料组件被装载到核心的最外部位置，而高浓缩燃料组件被装载到除了最外部位置之外的区域中。在这种布置中，重新加载燃料组件的平均富集为3.7重量％。

5. 发明授权

US06335956B1 Fuel assembly 有权
标题翻译：燃油组件
公开(公告)号：US06335956B1
公开(公告)日：2002-01-01
申请号：US09502334
申请日：2000-02-11
申请人： Junichi Koyama , Motoo Aoyama , Koji Nishida , Junichi Yamashita
发明人： Junichi Koyama , Motoo Aoyama , Koji Nishida , Junichi Yamashita
IPC分类号： G21C332
CPC分类号： G21C3/328 , Y02E30/38
摘要： Each of short-length fuel rods 3 is arranged at a position other than in 3×3 corner regions 6 to 9 in such a manner as not to be simultaneously adjacent to a water rod 5 and others of the short-sized fuel rods. Gd fuel rods 4 are arranged at positions excluding the outer periphery, and the number of those of the Gd fuel rods 4 adjacent to the short-length fuel rods 3 is one-half or less the total number of the Gd fuel rods. At a transverse cross-section of a region upward from upper ends of the short-sized fuel rods 3, the amount of burnable poison contained in a polygonal region 10 whose vertexes are located at centers of those of the first fuel rods 3 arranged at the outermost layer is smaller than the amount of burnable poison outside the region 10. With this configuration, a critical power can be improved in consideration of both a distribution of the flow of coolant and a distribution of a thermal power in the fuel assembly.
摘要翻译：短长度的燃料棒3中的每一个都配置在不同于3×3角区域6〜9的位置，不能与短棒燃料棒的水杆5等同时相邻。 Gd燃料棒4配置在除了外周的位置，并且与短长度燃料棒3相邻的Gd燃料棒4的数量是Gd燃料棒的总数的一半以下。在从小型燃料棒3的上端向上方的区域的横截面上，包含在多边形区域10中的可燃毒物的量，其顶点位于布置在第一燃料棒3的第一燃料棒3的顶点的中心最外层的面积小于区域10外部的可燃毒物的量。利用这种结构，考虑到冷却剂的流动分布和燃料组件中的火力分配两者，可以提高临界功率。

6. 发明授权

US6061416A Fuel assembly 失效
公开(公告)号：US6061416A
公开(公告)日：2000-05-09
申请号：US22678
申请日：1998-02-12
申请人： Junichi Koyama , Motoo Aoyama , Koji Nishida , Junichi Yamashita
发明人： Junichi Koyama , Motoo Aoyama , Koji Nishida , Junichi Yamashita
IPC分类号： G21C3/328 , G21C3/32 , G21C3/00 , G21C3/30
CPC分类号： G21C3/328 , Y02E30/38
摘要： Each of short-length fuel rods 3 is arranged at a position other than in 3.times.3 corner regions 6 to 9 in such a manner as not to be simultaneously adjacent to a water rod 5 and others of the short-sized fuel rods. Gd fuel rods 4 are arranged at positions excluding the outer periphery, and the number of those of the Gd fuel rods 4 adjacent to the short-length fuel rods 3 is one-half or less the total number of the Gd fuel rods. At a transverse cross-section of a region upward from upper ends of the short-sized fuel rods 3, the amount of burnable poison contained in a polygonal region 10 whose vertexes are located at centers of those of the first fuel rods 3 arranged at the outermost layer is smaller than the amount of burnable poison outside the region 10. With this configuration, a critical power can be improved in consideration of both a distribution of the flow of coolant and a distribution of a thermal power in the fuel assembly.

7. 发明授权

US5781604A Initial core and fuel assembly 失效
标题翻译：初始核心和燃料组装
公开(公告)号：US5781604A
公开(公告)日：1998-07-14
申请号：US727008
申请日：1996-10-08
申请人： Katsumasa Haikawa , Akihiro Yamanaka , Akiko Kanda , Motoo Aoyama , Yoko Yuchi , Junichi Yamashita
发明人： Katsumasa Haikawa , Akihiro Yamanaka , Akiko Kanda , Motoo Aoyama , Yoko Yuchi , Junichi Yamashita
IPC分类号： G21C5/12 , G21C3/32 , G21C3/326 , G21C3/328 , G21C3/62 , G21C5/00 , G21C5/02 , G21C7/113 , G21C3/00
CPC分类号： G21C5/02 , G21C3/328 , Y02E30/38
摘要： In an initial core of the present invention, a low enrichment fuel assembly having the lowest average enrichment factor and three fuel assemblies having a higher average enrichment factor than that of the low enrichment fuel assembly are arranged in a square shape, control rods of a cross shape are arranged at each of four corners of the square shape to constitute a unit loading pattern, and a plurality of the unit loading patterns are provided in the central region of the core, the fuel assemblies having the higher average enrichment factor are divided by a diagonal line into a first region of the side of the control rods and a second region of the side opposite to the control rods, and the number of the gadolinia-containing fuel rods is greater in the second region by at least two than in the first region. The initial core having an enhanced average enrichment factor for accomplishing a high exposure, makes it possible to maintain thermal margin, to suitably suppress the excess reactivity and to improve fuel economy.
摘要翻译：在本发明的初始核心中，具有最低平均富集因子的低富集燃料组件和具有比低浓度燃料组件更高的平均富集因子的三个燃料组件布置成正方形，十字形控制棒形状被布置在方形的四个角中的每一个角上以构成单元加载模式，并且在芯的中心区域中设置多个单元加载模式，具有较高平均富集因子的燃料组件被除以对角线插入到控制棒的一侧的第一区域和与控制棒相对的一侧的第二区域，并且含氧化钆的燃料棒的数量在第二区域中比在第一区域中的至少两个更大地区。具有增强的平均富集因子的初始核心用于实现高暴露，使得可以保持热裕度，以适当地抑制过量反应性并提高燃料经济性。

8. 发明授权

US5388132A Nuclear fuel assembly and core 失效
标题翻译：核燃料组件和核心
公开(公告)号：US5388132A
公开(公告)日：1995-02-07
申请号：US121898
申请日：1993-09-16
申请人： Motoo Aoyama , Yasunori Bessho , Junichi Yamashita , Katsumasa Haikawa , Hajime Umehara , Osamu Yokomizo , Hideo Soneda , Mitsunari Nakamura
发明人： Motoo Aoyama , Yasunori Bessho , Junichi Yamashita , Katsumasa Haikawa , Hajime Umehara , Osamu Yokomizo , Hideo Soneda , Mitsunari Nakamura
IPC分类号： G21C3/328 , G21C3/62
CPC分类号： G21C3/328 , G21Y2002/201 , G21Y2004/10 , G21Y2004/30 , Y02E30/31 , Y02E30/38
摘要： A mean uranium enrichment of fuel rods is set to not less than 4 wt% and preferably 4.25%, a percentage in number of Gd rods to all the fuel rods is set in the range of 20 to 30% and preferably 23%, and an enrichment 4.45 wt% of the Gd rods is between a pellet maximum uranium enrichment and a pellet minimum uranium enrichment. A percentage in number of those fuel rods having a maximum uranium enrichment of 5.0% to all the fuel rods except the Gd rods is set to not less than 75% and preferably 82%. A mean uranium enrichment in the enriched fuel section except blanket regions at upper and lower end portions is 4.75 wt% and a ratio e.sub.max /e.sub.mean of the pellet maximum uranium enrichment to that mean uranium enrichment is not larger than 1.16 and preferably 1.105. Accordingly, when the maximum uranium enrichment is limited to 5.0 wt%, the mean uranium enrichment can be raised to attain mean discharged exposure not less than 45 GWd/t without causing any problems in gadolinia containing fuel rods.
摘要翻译：将燃料棒的平均铀浓缩设定为不低于4重量％，优选为4.25％，将所有燃料棒的Gd棒的数量设定在20〜30％，优选为23％的范围内，富集4.45重量％的Gd棒是在颗粒最大铀浓缩和沉淀最小铀浓缩之间。对除了Gd棒以外的所有燃料棒，具有5.0％的最大铀浓缩的燃料棒的数量的百分比设定为75％以上，优选为82％。富集燃料部分的平均铀浓缩除上下部分的覆盖区域为4.75重量％，并且颗粒最大铀浓缩与该平均铀浓缩物的比例emax / emean不大于1.16，优选为1.105。因此，当最大铀浓缩限制为5.0重量％时，可以提高平均铀浓缩以达到不低于45GWd / t的平均排放暴露，而不会在含钆燃料棒中引起任何问题。

9. 发明授权

US07970094B2 Nuclear power plant and operation method thereof 有权
标题翻译：核电厂及其运行方法
公开(公告)号：US07970094B2
公开(公告)日：2011-06-28
申请号：US11968502
申请日：2008-01-02
申请人： Kazuaki Kitou , Masao Chaki , Kouji Shiina , Motoo Aoyama , Masaya Ohtsuka , Masayuki Nagasawa , Minoru Okura , Seiji Nemoto , Yasuhiro Takahashi
发明人： Kazuaki Kitou , Masao Chaki , Kouji Shiina , Motoo Aoyama , Masaya Ohtsuka , Masayuki Nagasawa , Minoru Okura , Seiji Nemoto , Yasuhiro Takahashi
IPC分类号： G21C7/00 , G21C17/00 , G21C7/32
CPC分类号： G21C1/08 , G21D3/00 , G21Y2002/201 , G21Y2004/30 , G21Y2004/40 , Y02E30/39
摘要： A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant 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. The operation method includes decreasing a ratio of extraction steam which is led to the feedwater heater from a steam loop in the second operation cycle.
摘要翻译：一种核电站和操作方法，用于在第二操作周期中将第二反应堆热功率输出增加到大于先前操作周期中的第一反应堆热功率输出的水平。该工厂装备有例如反应堆; 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。操作方法包括在第二操作循环中从蒸汽回路减少引导给水加热器的抽取蒸汽的比例。

10. 发明申请

US20080181349A1 Nuclear Power Plant and Operation Method Thereof 有权
标题翻译：核电厂及其运行方式
公开(公告)号：US20080181349A1
公开(公告)日：2008-07-31
申请号：US11968502
申请日：2008-01-02
申请人： Kazuaki Kitou , Masao Chaki , Kouji Shiina , Motoo Aoyama , Masaya Ohtsuka , Masayuki Nagasawa , Minoru Okura , Seiji Nemoto , Yasuhiro Takahashi
发明人： Kazuaki Kitou , Masao Chaki , Kouji Shiina , Motoo Aoyama , Masaya Ohtsuka , Masayuki Nagasawa , Minoru Okura , Seiji Nemoto , Yasuhiro Takahashi
IPC分类号： G21C7/32
CPC分类号： G21C1/08 , G21D3/00 , G21Y2002/201 , G21Y2004/30 , G21Y2004/40 , Y02E30/39
摘要： A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant 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. The operation method includes decreasing a ratio of extraction steam which is led to the feedwater heater from a steam loop in the second operation cycle.
摘要翻译：一种核电站和操作方法，用于在第二操作周期中将第二反应堆热功率输出增加到大于先前操作周期中的第一反应堆热功率输出的水平。该工厂装备有例如反应堆; 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。操作方法包括在第二操作循环中从蒸汽回路减少引导给水加热器的抽取蒸汽的比例。

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