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31. 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％。

32. 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。

33. 发明授权

US5176877A Nuclear fuel assembly and nuclear reactor core containing said assembly 失效
标题翻译：核燃料组件和核反应堆核心含有组装
公开(公告)号：US5176877A
公开(公告)日：1993-01-05
申请号：US584745
申请日：1990-09-19
申请人： Akinobu Nakajima , Yasunori Bessho , Motoo Aoyama , Junichi Koyama , Hiromasa Hirakawa , Junichi Yamashita , Tatsuo Hayashi
发明人： Akinobu Nakajima , Yasunori Bessho , Motoo Aoyama , Junichi Koyama , Hiromasa Hirakawa , Junichi Yamashita , Tatsuo Hayashi
IPC分类号： G21C3/328 , G21C3/326
CPC分类号： G21C3/326 , G21Y2002/201 , G21Y2004/30 , Y02E30/38
摘要： A nuclear fuel assembly for a nuclear reactor has a plurality of vertically extending fuel rods arranged side by side in a square array and containing fissile material. The array has two adjacent first sides which are next to a control rod region of the core and two adjacent second sides which are next to a non-control rod region of the core. When the rods of the array as seen in horizontal cross section, excluding the rods lying on the diagonal line joining the opposite corners of the array at which the control rod region meets the non-control rod region, is divided into four regions which area: the rods in the row and column of said array adjoining said first sides;b: the rods lying between said region a and said diagonal line;c: the rods lying between said region d and said diagonal line,d: the rods in the row and column of said array adjoining said second sides and; over at east part of the height containing fissile material, the average concentration of fissile material per fuel rod is higher in said region b than said region c and by at least 5% and, among all said regions a, b, c, d, is a minimum in said region a. This provides good control rod worth and low local power peaking.

34. 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℃。

35. 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.

36. 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℃。

37. 发明授权

US07349518B2 Boiling water reactor core and fuel assemblies therefor 有权
标题翻译：沸水堆芯和燃料组件
公开(公告)号：US07349518B2
公开(公告)日：2008-03-25
申请号：US11376415
申请日：2006-03-16
申请人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
发明人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
IPC分类号： G21C3/32
CPC分类号： G21C3/326 , G21C1/084 , G21C3/32 , G21C5/18 , Y02E30/31 , Y02E30/38
摘要： A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxidecontaining not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
摘要翻译：加载在核心上的燃料组件的数量与控制棒驱动机构的数量的比率为3以上。燃料组件本身含有燃料组合物的平均富集浓度为3〜8重量％的低浓度浓度铀氧化物的混合氧化物，或平均浓度为2重量％以上但小于6重量％的混合氧化物易裂变钚的浓缩浓度。在装有燃料组件的燃烧器型BWR铁心中，作为未燃烧状态值的转化率，铀，钚和次锕系元素的平均重量密度为2.1〜3.4kg / L。

38. 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。

39. 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。

40. 发明授权

US5093070A Core loading strategy 失效
标题翻译：核心加载策略
公开(公告)号：US5093070A
公开(公告)日：1992-03-03
申请号：US448209
申请日：1989-12-08
申请人： Junichi Koyama , Motoo Aoyama , Akinobu Nakajima , Hiromi Maruyama
发明人： Junichi Koyama , Motoo Aoyama , Akinobu Nakajima , Hiromi Maruyama
IPC分类号： G21C5/00 , G21C5/18 , G21C7/00 , G21C19/20
CPC分类号： G21C19/205 , G21C7/00 , G21Y2002/201 , G21Y2004/10 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： A core of boiling water reactor is divided into a central region and a peripheral region surrounding it in the radial direction thereof. The loading fraction of new first fuel assemblies containing burnable poison and loaded in the central region is greater than the loading fraction of the new first fuel assemblies loaded in the peripheral region. The loading fraction of second fuel assemblies loaded in the central region of the core and operating in a second operation cycle is smaller than the loading fraction of the second fuel assemblies loaded in the peripheral region of the core and operating in the second operation cycle. The second fuel assemblies contain no burnable poison. In such a core, the reactivity of the peripheral region is greater than that of the central region in the beginning of an operation cycle. Contrary, the reactivity of the central region is greater than that of the peripheral region in the end of an operation cycle.
摘要翻译：沸水反应器的核心沿径向方向被分为中心区域和围绕它的周边区域。包含可燃毒物并装载在中心区域的新的第一燃料组件的负载分数大于装载在周边区域中的新的第一燃料组件的负载分数。负载在芯的中心区域并在第二操作循环中操作的第二燃料组件的负载分数小于装载在铁芯的周边区域并在第二操作循环中操作的第二燃料组件的负载分数。第二燃料组件不含可燃毒物。在这样的核心中，在操作周期开始时，周边区域的反应性大于中心区域的反应性。相反，在操作周期结束时，中心区域的反应性大于外围区域的反应性。

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