Fuel assembly and reactor core
    2.
    发明授权
    Fuel assembly and reactor core 失效
    燃料组件和反应堆堆芯

    公开(公告)号:US5383229A

    公开(公告)日:1995-01-17

    申请号:US879

    申请日:1993-01-05

    IPC分类号: G21C3/328 G21C3/32

    摘要: A second fuel rod positioned at each corner of a channel box and second fuel rods adjacent to the former are formed to have a smaller outer diameter than that of ordinary first fuel rods, so that a pitch between the second fuel rods is narrower than a pitch between the first fuel rods. Making the outer diameter of the second fuel rods smaller than that of the first fuel rods reduces the power per unit length of the second fuel rods. The narrower pitch between the second fuel rods than the pitch between the first fuel rods provides two effects. First, a unit lattice cell becomes so small as to avoid an increase in the H/U ratio. Secondly, a new moderator region is formed between the second fuel rods and the first fuel rods adjacent thereto, the moderator region acting to intensify thermal neutron flux around those first fuel rods. These two effects enable a further reduction in the power per unit length of the second fuel rods. As a result, a fuel assembly intended for higher burn-up can be realized by increasing enrichment, while suppressing an increase in the local power peaking factor at corners of the fuel assembly.

    摘要翻译: 定位在通道箱的每个角落处的第二燃料棒和与前者相邻的第二燃料棒形成为具有比普通的第一燃料棒小的外径,使得第二燃料棒之间的间距比间距窄 在第一燃料棒之间。 使得第二燃料棒的外径小于第一燃料棒的外径减小了第二燃料棒的每单位长度的功率。 第二燃料棒之间的间距窄于第一燃料棒之间的间距,提供了两个效果。 首先,单位晶胞变得如此小以避免H / U比的增加。 其次,在第二燃料棒和与其相邻的第一燃料棒之间形成新的慢化剂区域,该慢化剂区域用于加强围绕这些第一燃料棒的热中子通量。 这两个效果使得能够进一步降低第二燃料棒的每单位长度的功率。 结果,可以通过增加浓缩来实现用于更高燃耗的燃料组件,同时抑制燃料组件的角落处的局部功率峰值因数的增加。

    Fuel assembly
    3.
    发明授权
    Fuel assembly 失效
    燃油组件

    公开(公告)号:US5337337A

    公开(公告)日:1994-08-09

    申请号:US857263

    申请日:1992-03-25

    IPC分类号: G21C3/30 G21C3/328 G21C3/32

    摘要: A fuel assembly comprising a plurality of fuel rods, where fuel rods containing a burnable poison element having a smaller neutron absorption cross-section such as boron are provided in a region of soft neutron energy spectrum and a large thermal neutron flux and fuel rods containing a burnable poison element having a larger neutron absorption cross-section such as gadolinium and fuel rods containing no such burnable poison element are provided in other region of average neutron energy spectrum, has a flat fuel rod power distribution throughout the fuel lifetime even against substantially uniform uranium enrichment distribution with reduced parasitic neutron absorption by gadolia, that is, with higher burnup and reduced fuel cycle cost.

    摘要翻译: 一种燃料组件,其包括多个燃料棒,其中在软中子能谱范围内设置含有具有较小中子吸收截面的可燃毒元素的燃料棒,例如硼,并且包含大量热中子通量和含有 在其他平均中子能谱区域中提供了具有较大中子吸收截面的可燃毒物元素,例如钆和不含这种可燃毒物元素的燃料棒,在整个燃料使用寿命期间具有扁平的燃料棒功率分布,甚至基本上均匀的铀 浓缩分布减少钆的寄生中子吸收,即燃耗增加和燃料循环成本降低。

    Fuel loading method and reactor core
    4.
    发明授权
    Fuel loading method and reactor core 失效
    燃料加载方法和反应堆堆芯

    公开(公告)号:US5307387A

    公开(公告)日:1994-04-26

    申请号:US918596

    申请日:1992-07-24

    摘要: In a fuel loading method for a reactor core made up by high burn-up fuel, fuel assemblies loaded in a circumferential zone of the core are shuffled between two layers of the circumferential zone until residing in the core for two cycles and, after residing for two cycles, are moved to the fourth layer of the circumferential zone from an outermost layer of the core, thereby reducing the difference in exposure due to a different radial power level in the vicinity of the core boundary. Those fuel assemblies are moved to control cells in a central zone of the core after residing in the circumferential zone for three cycles, and also such fuel assemblies as having resided in the central zone for three cycles are moved to the core outermost layer, thereby reducing the difference in exposure between the fuel assemblies having resided in the central zone and the fuel assemblies having resided in the circumferential zone due to different power levels in the central and circumferential zones. As a result, the difference in exposure between used fuel assemblies is reduced.

    摘要翻译: 在由高燃耗燃料构成的反应堆堆芯的燃料装载方法中,装载在芯的圆周区域的燃料组件在周向区域的两层之间被洗牌,直到驻留在铁芯中两个循环,并且在驻留 两个周期从芯的最外层移动到周向区的第四层,从而减小由于在核心边界附近的不同径向功率水平引起的曝光差异。 这些燃料组件在驻留在周向区域中三个循环之后移动到核心的中心区域中的控制室,并且也将驻留在中心区域中的三个循环的这种燃料组件移动到芯最外层,从而减少 由于在中心区域和周边区域中的功率水平不同,已经驻留在中心区域中的燃料组件和位于周向区域中的燃料组件之间的曝光差异。 结果,使用的燃料组件之间的曝光差减小。

    Fuel assembly
    5.
    发明授权
    Fuel assembly 失效
    燃油组件

    公开(公告)号:US4689195A

    公开(公告)日:1987-08-25

    申请号:US635927

    申请日:1984-07-30

    IPC分类号: G21C3/32 G21C3/328 G21C7/00

    摘要: In a nuclear reactor, gaps are defined between fuel assemblies so that moderators can be inserted. Hence, the nuclear characteristics vary between the central portion and periphery of the fuel assembly so that the local output peaking becomes greater on the periphery of the fuel assembly. The present invention flattens the local output peaking by providing that the quantity of a nuclear fuel material per fuel rod loaded in the fuel rods on the periphery of the fuel assembly is smaller than the quantity of the fuel material per fuel rod loaded in the fuel rods at the central portion of the fuel assembly. Any one of the following three constructions can be used:(1) The theoretical density of the nuclear fuel material pellets to be inserted into the fuel rod is reduced.(2) The nuclear fuel material pellets to be inserted into the fuel rod is made hollow.(3) The diameter of the fuel rod is reduced.

    摘要翻译: 在核反应堆中,在燃料组件之间限定了间隙,从而可以插入调节器。 因此,核特性在燃料组件的中心部分和周边之间变化,使得局部输出峰值在燃料组件的周边上变得更大。 本发明通过设置装载在燃料组件周边上的燃料棒中的每个燃料棒的核燃料材料的数量小于装载在燃料棒中的每个燃料棒的燃料材料的数量来使局部输出峰值平坦化 在燃料组件的中心部分。 可以使用以下三种结构中的任何一种:(1)减少插入到燃料棒中的核燃料材料颗粒的理论密度。 (2)插入燃料棒的核燃料材料粒料为中空状。 (3)燃料棒的直径减小。

    Reactor
    6.
    发明授权
    Reactor 失效
    反应堆

    公开(公告)号:US5037607A

    公开(公告)日:1991-08-06

    申请号:US354780

    申请日:1989-05-22

    摘要: The present invention provides a structural component for constituting a reactor core comprising one and the other metallic members arranged adjacent to each other in a reactor, and reduction means for reducing a difference in the swelling between the metallic members due to neutron irradiation thereto; a core of the reactor comprising a plurality of such constructural element; and a method for operating a reactor having metallic tubular members arranged in a core of the reactor and each enclosing a plurality of metallic cladding tubes in each of which substance heated by neutron irradiation thereto and cooled by passing coolant through the reactor core is filled, wherein the reactor is operated under a condition that an average used temperature of the cladding tubes is higher than an irradiation temperature that the swelling rate of the cladding material due to neutron irradiation thereto becomes maximum and an average used temperature of the tubular members is lower than an irradiation temperature that the swelling rate of the tubular material due to neutron irradiation thereto becomes maximum. According to the structural component and the reactor core, since the difference in the swelling between the metallic members due to neutron irradiation thereto can be decreased, any mechanical interactions can be prevented or reduced. According to the present method, since the difference in the swelling between the metallic members due to neutron irradiation thereto can be decreased due to the above operation temperature condition, any mechanical interactions can be prevented or reduced.

    Fast breeder reactor
    7.
    发明授权
    Fast breeder reactor 失效
    快速增殖反应堆

    公开(公告)号:US4762672A

    公开(公告)日:1988-08-09

    申请号:US787390

    申请日:1985-10-15

    IPC分类号: G21C7/10 G21C7/103 G21C7/27

    摘要: In a fast breeder reactor provided with a core comprising a core region packed with a fissile material and a blanket region which surrounds the outside of said core region and most of which is formed of a fertile material, and a plurality of control rods which are put in and out of the above core region by a control rod driving device, the fast breeder reactor of the present invention is characterized in that each of said control rods is constructed of a neutron absorber region packed with a neutron absorber and a gas region disposed in the end portion on the side further separated from said control rod driving device than said neutron absorber region. With this invention, the spectral shift effect can be produced by utilizing said gas region, thereby increasing the core reactvity of the fast breeder reactor.

    摘要翻译: 在具有核心的快速增殖反应器中,该核心包括填充有易裂变材料的核心区域和围绕所述核心区域的外部的覆盖区域,并且大部分由可育材料形成,并且多个控制棒被放置 通过控制棒驱动装置进出上述芯区域,本发明的快速增殖反应器的特征在于,每个所述控制棒由填充有中子吸收器的中子吸收体区域和设置在 与所述中子吸收体区域相比,与所述控制棒驱动装置分离的一侧的端部。 利用本发明,通过利用所述气体区域可以产生光谱偏移效应,从而提高快速增殖反应堆的核心反应性。

    Boiling water type nuclear reactor
    10.
    发明授权
    Boiling water type nuclear reactor 失效
    沸水型核反应堆

    公开(公告)号:US4292128A

    公开(公告)日:1981-09-29

    申请号:US942558

    申请日:1978-09-15

    摘要: A boiling water type nuclear reactor adapted to be operated at a void quality (weight ratio of vapor in the coolant) of coolant at the core outlet of 17% or higher. By adopting this level of void quality, a void quality exceeding 8.5% is available at least in the upper half region of the core which in turn provides a void fraction of 66% or higher. Consequently, it is possible to reduce the enrichment of the fuel, so as to allow a more efficient use of the fuel. At the same time, due to the reduced power generating rate, the range over which the flow rate of coolant is controlled is widened, so that it becomes possible to change the reactivity solely by controlling the flow rate of the coolant. It is therefore possible to operate the reactor over whole operation cycle with its control rods fully withdrawn.

    摘要翻译: 一种沸水型核反应堆,适于在核心出口处的冷却剂的空隙质量(冷却剂中的蒸汽的重量比)为17%或更高的温度下操作。 通过采用该水平的空隙质量,至少在芯的上半部区域可以获得超过8.5%的空隙质量,这又提供66%或更高的空隙率。 因此,可以减少燃料的浓缩,从而更有效地利用燃料。 同时,由于发电率降低,控制冷却剂流量的范围扩大,从而可以通过控制冷却剂的流量来改变反应性。 因此,可以在整个操作周期内操作反应器,其控制棒完全拉出。