Nuclear power plant and operation method thereof
    21.
    发明申请
    Nuclear power plant and operation method thereof 有权
    核电厂及其运行方法

    公开(公告)号:US20050220253A1

    公开(公告)日:2005-10-06

    申请号:US11033953

    申请日:2005-01-13

    IPC分类号: G21C1/08 G21C19/00 G21D3/00

    摘要: A nuclear power plant of the invention 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, and an operation method thereof is characterized by augmenting a second reactor thermal power output in a second operation cycle of the reactor larger than a first reactor thermal power output in a first operation cycle; and making an increase ratio of extraction steam, which is led to the feedwater heater with being extracted from the steam loop, in the second operation cycle for the first operation cycle smaller than an increase ratio of the second reactor thermal power output for the first reactor thermal power output.

    摘要翻译: 本发明的核电站例如配备有反应器; 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及其操作方法的特征在于,在反应器的第二操作循环中增加第二反应堆热功率输出,其大于第一反应堆热功率输出 操作周期; 并且在第一操作循环的第二操作循环中,使第一反应器的第二反应堆热功率输出的增加比率小于从蒸汽回路引出的给水加热器的提取比例增加 火力输出。

    Initial core and fuel assembly
    24.
    发明授权
    Initial core and fuel assembly 失效
    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

    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。

    Initial Core of Nuclear Reactor and Method of Loading Fuel Assemblies of Nuclear Reactor
    25.
    发明申请
    Initial Core of Nuclear Reactor and Method of Loading Fuel Assemblies of Nuclear Reactor 审中-公开
    核反应堆的初始核心和核反应堆装载燃料组件的方法

    公开(公告)号:US20130051509A1

    公开(公告)日:2013-02-28

    申请号:US13594213

    申请日:2012-08-24

    IPC分类号: G21C19/04 G21C7/06 G21C15/02

    摘要: In an initial core of a nuclear reactor, a plurality of water regions having a square cross section for occupying a cross sectional area capable of disposing four fuel assemblies are formed. No fuel assemblies are loaded in these water regions. In the initial core, each fuel assembly is supported by fuel supports. A pressure loss of a first orifice installed in a cooling water supply passage formed in first fuel supports disposed in a central portion of the initial core is larger than that of a second orifice installed in a cooling water supply passage formed in second fuel supports disposed in a peripheral portion surrounding the central portion. Each water region is formed right above a part of the first fuel supports disposed in the central portion. The control rod operation in the nuclear reactor can be simplified by action of cooling water in the water regions.

    摘要翻译: 在核反应堆的初始核心中,形成具有正方形横截面的多个水区域,用于占据能够设置四个燃料组件的横截面积。 在这些水域中没有装载燃料组件。 在初始核心中,每个燃料组件由燃料支撑件支撑。 安装在设置在初始芯部的中心部分的第一燃料支架中的冷却水供应通道中的第一孔口的压力损失大于安装在设置在第二燃料支架中的第二燃料支架中形成的冷却水供应通道中的第二孔口的压力损失 围绕中心部分的周边部分。 每个水区形成在布置在中心部分中的第一燃料支架的一部分的正上方。 核反应堆中的控制杆操作可以通过在水域中冷却水的作用来简化。

    Operation method of nuclear power plant
    26.
    发明授权
    Operation method of nuclear power plant 有权
    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

    IPC分类号: G21D5/00 F01K7/34

    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℃。

    Operation method of nuclear power plant
    28.
    发明授权
    Operation method of nuclear power plant 有权
    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

    IPC分类号: G21D5/00

    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℃。

    Boiling water reactor core and fuel assemblies therefor
    29.
    发明授权
    Boiling water reactor core and fuel assemblies therefor 有权
    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

    IPC分类号: G21C3/32

    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。

    Fuel assembly
    30.
    发明授权
    Fuel assembly 有权
    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

    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。