Fuel assembly
    1.
    发明授权
    Fuel assembly 失效
    燃油组件

    公开(公告)号:US5299244A

    公开(公告)日:1994-03-29

    申请号:US772440

    申请日:1991-10-07

    IPC分类号: G21C3/326 G21C3/328 G21C3/34

    摘要: A plurality of fuel rods containing fissile material are arranged in triangle lattices. A plurality of water rods groups are arranged among the fuel rods. Each of the water rods groups includes no fuel rod but a plurality of water rods which are arranged adjacently each other in triangle lattices having substantially same pitch as the fuel rods. The water rods groups are arranged not adjacently each other, and are surrounded with the fuel rods. the outer diameter of the water rod is smaller than the pitch. The fuel assembly is able to suppress increment of pressure loss because of formation of coolant path among adjacent water rods. Further, void reactivity coefficient is able to be small.

    摘要翻译: 包含易裂变材料的多个燃料棒被布置成三角形格子。 燃料棒之间布置有多个水杆组。 每个水棒组不包括燃料棒,而是包括与燃料棒具有基本相同节距的三角形格架相邻布置的多个水杆。 水杆组彼此相邻配置,并被燃料棒包围。 水杆的外径小于间距。 燃料组件由于在相邻的水棒之间形成冷却剂路径而能够抑制压力损失的增加。 此外,空隙反应性系数能够小。

    Fuel assembly
    2.
    发明授权
    Fuel assembly 失效
    燃油组件

    公开(公告)号:US5528641A

    公开(公告)日:1996-06-18

    申请号:US357261

    申请日:1994-12-13

    摘要: A fuel assembly is provided with a coolant ascending path for making coolant rise and a water rod having a coolant descending path for conducting the coolant.A ratio of a flow area in a coolant inlet port of the smallest in coolant ascending path 13 on the downstream side than large diameter tube portion 3E to a flow area of the largest in the axial direction of coolant ascending path 13 in large diameter tube portion 3E is set to be 0.2-20%.In the normal operation, the declination degree from the liquid level in the coolant ascending path, corresponding to the coolant flow rate of the liquid level formed in the coolant ascending path can be controlled. Further, at the time of the excess the change speed of the liquid level can also be controlled.

    摘要翻译: 燃料组件设置有用于使冷却剂升起的冷却剂上升路径和具有用于导引冷却剂的冷却剂下降路径的水杆。 在大直径管部3E的下游侧的冷却剂上升路径13中的最小的冷却剂入口的流入面积与大径管部中的冷却剂上升路径13的轴向上最大的流动面积的比 3E设定为0.2〜20%。 在正常操作中,可以控制与冷却剂上升路径中形成的液面的冷却剂流量相对应的冷却剂上升路径中的液位的偏角度。 此外,在过量时,也可以控制液面的变化速度。

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

    公开(公告)号:US4876062A

    公开(公告)日:1989-10-24

    申请号:US172418

    申请日:1988-03-24

    摘要: A fuel assembly of the present invention comprises a plurality of fuel rods which are held by an upper tie plate and lower tie plate at the ends thereof and a moderating rod which is arranged between the fuel rods and held by the lower tie plate at its lower end. The fuel rods are arranged in a lattice form having 9 rows and 9 columns, and the moderating rod contains a passage for a coolant and has a cruciate cross-sectional form. The ratio A.sub.M /A.sub.C of the area A.sub.M of a moderator region in the moderating rod in the cross-sectional plane in which the moderator is present to the area A.sub.C of the coolant passages in said fuel assembly is within the range of 0.07 to 0.11, and the area A.sub.M is 75% or more of the total area of the fuel lattice units in which none of the fuel rods is arranged, but the moderating rod is arranged.

    Fuel assembly and nuclear reactor
    4.
    发明授权
    Fuel assembly and nuclear reactor 失效
    燃料装配和核反应堆

    公开(公告)号:US5617456A

    公开(公告)日:1997-04-01

    申请号:US463828

    申请日:1995-06-05

    IPC分类号: G21C3/328 G21C21/00

    CPC分类号: G21C3/328 Y02E30/38

    摘要: The lower end of each of a plurality of fuel rods is supported by a fuel supporting portion of a lower tie plate. The fuel supporting portion includes a plurality of second coolant paths for supplying a coolant from below the fuel supporting portion to a first coolant path defined above the fuel supporting portion and between the fuel rods. The total cross-sectional area of all the second coolant paths is smaller than the cross-sectional area of the first coolant path. A water rod disposed between the fuel rods each includes an ascending tube path having therein a coolant ascending path having a coolant inlet port opening to a region below the fuel supporting portion, for guiding upward the coolant supplied through the coolant inlet port, and a descending tube having therein a coolant descending path having a coolant delivery port opening to said first coolant path, for guiding downward the coolant guided by said coolant ascending path and discharging the coolant through the coolant delivery port to the first coolant path. The descending tube path is so disposed outside the ascending tube path as to define a gap, through which the coolant inside the first coolant path flows, between it and the ascending tube path.

    摘要翻译: 多个燃料棒的每一个的下端由下连接板的燃料支撑部支撑。 燃料支撑部分包括多个第二冷却剂路径,用于将冷却剂从燃料支撑部分下方供应到限定在燃料支撑部分上方和燃料棒之间的第一冷却剂路径。 所有第二冷却剂通道的总截面积小于第一冷却剂通道的横截面面积。 设置在燃料棒之间的水杆各自包括上升管路,其中具有冷却剂上升路径,其具有通向燃料支撑部分下方的区域的冷却剂入口,用于向上引导通过冷却剂入口提供的冷却剂, 其中具有冷却剂下降路径,其具有通向所述第一冷却剂路径的冷却剂输送口,用于向下引导由所述冷却剂上升路径引导的冷却剂并将冷却剂通过冷却剂输送端口排出到第一冷却剂路径。 下降的管道设置在上升管道的外侧,以便限定第一冷却剂路径内的冷却剂在其与上升的管道之间流动的间隙。

    Light water moderation type nuclear reactor
    5.
    发明授权
    Light water moderation type nuclear reactor 失效
    轻水缓和型核反应堆

    公开(公告)号:US4851181A

    公开(公告)日:1989-07-25

    申请号:US123542

    申请日:1987-11-20

    CPC分类号: G21C5/18 Y02E30/40

    摘要: In a light water moderation type nuclear reactor with the once-through method, the reactor core is divided into a central area and a peripheral area by a partition member, a first fuel assembly is arranged in the central area (high conversion area) and a second fuel assembly is arranged in the peripheral area. The ratio (r.sub.H/U) of the number of hydrogen atoms to that of uranium atoms in the central area is smaller than that of the ratio in the peripheral area and the second fuel assembly in the peripheral area is formed of fuel rods of the first fuel assembly having been previously burned in the central area and moved into the peripheral area. The plutonium production increases and uranium consumption is reduced during the first half of the lifetime of the fuel rods in the high conversion area with the take-up burn up increasing during the second half of the lifetime of the fuel rods in the burner area.

    摘要翻译: 在具有一次通过方法的轻水调节型核反应堆中,反应堆堆芯通过分隔构件分成中心区域和周边区域,第一燃料组件布置在中心区域(高转化区域)和 第二燃料组件布置在周边区域中。 中心区域的氢原子数与铀原子数的比值(rH / U)小于外围区域的比例,并且周边区域中的第二燃料组件的比率(rH / U)由第一 燃料组件先前已经在中心区域燃烧并移动到周边区域。 在高转化率区域的燃料棒的寿命的前半期,钚的生产增加,铀的消耗减少,在燃烧器区域的燃料棒的寿命的后半期,吸收燃烧增加。

    Fuel assembly
    6.
    发明授权
    Fuel assembly 失效
    燃油组件

    公开(公告)号:US5490192A

    公开(公告)日:1996-02-06

    申请号:US247854

    申请日:1994-05-23

    IPC分类号: G21C3/344 G21C3/34

    摘要: A fuel assembly comprises a plurality of fuel rods, tie plates for holding both ends of these fuel rods, and spacers which support these fuel rods. The spacer comprises a plurality of cells into which the fuel rods are inserted respectively, the adjacent cells being joined to each other at axial ends thereof, whereby a space between these cells being held or retained, and a plurality of loop springs held respectively on the cells. Each of the loop springs has a pair of resilient members which are located within the pair of adjacent cells and which urge the fuel rods in a radial direction, and a pair of connections which connect axial ends of the resilient members to each other. Each of the connections have a passage through which coolant flows axially and which is defined by a closed peripheral wall. The closed peripheral wall is not uniform in thickness. The pair of adjacent cells have at axial end portions of peripheral walls openings for accommodating or receiving the connections of the loop spring.

    摘要翻译: 燃料组件包括多个燃料棒,用于保持这些燃料棒的两端的连接板以及支撑这些燃料棒的间隔件。 间隔件包括分别插入燃料棒的多个单元,相邻的单元在其轴向端部彼此接合,由此保持或保持这些单元之间的空间,以及分别保持在该单元上的多个环形弹簧 细胞。 每个环形弹簧具有一对弹性构件,该弹性构件位于一对相邻的单元内并且沿径向推动燃料棒,以及将弹性构件的轴向端部彼此连接的一对连接件。 每个连接件都有一个通道,冷却剂通过该通道轴向流动,并由封闭的外围壁限定。 封闭的周边壁厚度不均匀。 一对相邻的单元具有用于容纳或接收环形弹簧的连接的外围壁开口的轴向端部。

    Nuclear fuel assembly
    7.
    发明授权
    Nuclear fuel assembly 失效
    核燃料组件

    公开(公告)号:US5272741A

    公开(公告)日:1993-12-21

    申请号:US782812

    申请日:1991-10-25

    IPC分类号: G21C3/322 G21C3/344 G21C3/34

    摘要: A nuclear fuel assembly for a BWR comprises a plurality of fuel rods, a polygonal channel box surrounding the fuel rods, a plurality of spacers axially spaced from each other and each keeping the fuel rods laterally spaced from each other, and a plurality of vanes disposed only in a region at and around a corner within the channel box, for generating swirling flows in the region to thicken a liquid film on each fuel rod in the region.

    摘要翻译: 用于BWR的核燃料组件包括多个燃料棒,围绕燃料棒的多边形通道箱,多个彼此间隔开的间隔件,并且每个保持燃料棒彼此横向隔开,并且设置多个叶片 仅在通道箱内的拐角处和周围的区域中,用于在该区域中产生旋流以增加该区域中每个燃料棒上的液膜。

    Nuclear fuel assembly and core
    10.
    发明授权
    Nuclear fuel assembly and core 失效
    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

    IPC分类号: G21C3/328 G21C3/62

    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。