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公开(公告)号：US20090041174A1
公开(公告)日：2009-02-12
申请号：US12186560
申请日：2008-08-06
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： G21C15/06
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。
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公开(公告)号：US20120063561A1
公开(公告)日：2012-03-15
申请号：US13222366
申请日：2011-08-31
IPC分类号： G21C3/32
摘要： A fuel assembly has a constitution in which plural fuel rods are arranged in 10 rows by 10 columns in a channel box, and includes plural fuel rods G containing gadolinium and plural partial length fuel rods P. In the fuel assembly, average enrichment of lower portion cross section is approximately 4.6 wt %, and average enrichment of upper portion cross section is approximately 4.7 wt %. The average enrichments at the outermost layer are approximately 5.6 wt % both in the upper portion and the lower portion. Ratios e/x of the average enrichment of the outermost layer e (wt %) to the average enrichment of the fuel assembly cross section x (wt %) are 1.19 in the upper portion and 1.22 in the lower portion, and the ratios satisfy equation (1). [ Equation 1 ] e x ≥ - 18.3 ( x 10 ) 5 + 68.766 ( x 10 ) 4 - 101.77 ( x 10 ) 3 + 74.428 ( x 10 ) 2 - 27.372 ( x 10 ) + 5.1682 ( 1 )
摘要翻译： 燃料组件具有多个燃料棒在通道箱中以10行×10列排列的结构，并且包括含有钆和多个部分长度的燃料棒P的多个燃料棒G.在燃料组件中，下部的平均浓缩 横截面为约4.6重量％，上部截面的平均富集度为约4.7重量％。 最外层的平均浓度在上部和下部均为5.6重量％左右。 最外层e（wt％）对燃料组件横截面x（wt％）的平均富集度的平均富集比例e / x在上部为1.19，下部为1.22，比率满足式 （1）。 （x 10）4 - 101.77（x 10）3 + 74.428（x 10）2 - 27.372（x 10）+ 5.1682（x 10） （1）
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3.发明申请METHOD FOR OPERATING NUCLEAR POWER GENERATION PLANT AND NUCLEAR POWER GENERATION PLANT 审中-公开核动力发电厂和核发电厂的运行方法公开(公告)号：US20090141847A1
公开(公告)日：2009-06-04
申请号：US12324936
申请日：2008-11-28
申请人： Tetsushi HINO , Masao CHAKI , Motoo AOYAMA , Takeshi MITSUYASU , Yoshihiko ISHII
发明人： Tetsushi HINO , Masao CHAKI , Motoo AOYAMA , Takeshi MITSUYASU , Yoshihiko ISHII
摘要： An method for operating a nuclear power generation plant, comprising the steps of: forming a plurality of control rod patterns by operating a plurality of control rods during a first period of one operation cycle of a reactor including said first period before a point of time when all control rods are completely withdrawn from a core of said reactor and a core flow rate reaches firstly a set core flow rate, and a second period after said point of time, controlling stepwise at least once a temperature of feed water supplied to said reactor based on a different set feed water temperature during a period included in said first period for operating said reactor with a formed same control rod pattern, and continuing feed water temperature control based on said set feed water temperature until said core flow rate reaches a set core flow rate set based on said set feed water temperature.
摘要翻译： 一种用于操作核发电厂的方法，包括以下步骤：通过在包括所述第一时段的电抗器的一个操作周期的第一周期期间操作多个控制棒来形成多个控制棒图案， 所有控制棒从所述反应器的核心完全取出，并且芯流速率首先达到设定的核心流速，并且在所述时间点之后的第二时间段内，逐步控制供应到所述反应器的给水温度至少一次 在包括在用于以所形成的相同控制杆模式操作所述反应器的所述第一时段期间的不同设定进料水温度下，以及基于所述设定的给水温度继续供水温度控制，直到所述芯流量达到设定的芯流量 基于所述设定的给水温度设定速率。
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公开(公告)号：US20100170246A1
公开(公告)日：2010-07-08
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
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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公开(公告)号：US20110162363A1
公开(公告)日：2011-07-07
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
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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公开(公告)号：US20070274428A1
公开(公告)日：2007-11-29
申请号：US11668028
申请日：2007-01-29
申请人： Masao CHAKI , Tetsushi Hino
发明人： Masao CHAKI , Tetsushi Hino
IPC分类号： G21C19/42
摘要： The natural circulation type boiling water reactor comprises a core in which a plurality of fuel assemblies are loaded, and a chimney which is disposed above the core and has a path partition which forms a plurality of vertical lattice paths. A uniform pressure space is formed between the core and the chimney and not disposed the path partition. The two-phase flow including the cooling water and the steam exhausted from the core through the uniform pressure space is supplied to the vertical lattice paths. The two-phase flow ascends in the vertical lattice paths. Thus, the flow distribution for each fuel assembly can be calculated using the pressure difference between the upper end and the lower end of the core can be calculated without the need for the void fraction of the lattice paths.
摘要翻译： 自然循环式沸水反应堆包括其中装载有多个燃料组件的芯和设置在芯上方并且具有形成多个垂直格栅路径的路径分隔的烟囱。 在核心和烟囱之间形成均匀的压力空间，而不设置路径隔板。 包括冷却水和通过均匀压力空间从芯排出的蒸汽的两相流被提供给垂直格栅路径。 两相流在垂直格子路径中上升。 因此，可以计算出每个燃料组件的流量分布，而不需要格子路径的空隙率，可以计算出核心的上端和下端之间的压力差。
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