Method for producing a fuel rod
    5.
    发明授权
    Method for producing a fuel rod 失效
    燃料棒的制造方法

    公开(公告)号:US6103996A

    公开(公告)日:2000-08-15

    申请号:US283869

    申请日:1999-04-01

    IPC分类号: G21C21/02 B23K9/028 B23K9/167

    CPC分类号: B23K9/0286 B23K2201/06

    摘要: A method for manufacturing a fuel rod of the present invention includes a welding step of welding a cladding tube of said fuel rod to a plug by arc discharge; and a post welding step of subsequently discharging an arc to a welded portion by a predetermined arc current lower than that of the welding step. In the welding step and in the post welding step, the cladding tube and the plug are rotated with respect to an electrode for discharging the arc. The rotation speed of the cladding tube and the plug in the post welding step is higher than that in the welding step.

    摘要翻译: 本发明的燃料棒的制造方法包括:通过电弧放电将所述燃料棒的包覆管焊接到塞子上的焊接工序; 以及后焊接步骤,其随后以比焊接步骤低的预定电弧电流将电弧放电到焊接部分。 在焊接步骤和后焊步骤中,包层管和插塞相对于用于排出电弧的电极旋转。 后焊接工序中的包层管和插塞的转速高于焊接工序。

    Zirconium alloy for use in spacer grids for nuclear reactor fuel
claddings
    6.
    发明授权
    Zirconium alloy for use in spacer grids for nuclear reactor fuel claddings 失效
    用于核反应堆燃料包层的隔离栅的锆合金

    公开(公告)号:US5019333A

    公开(公告)日:1991-05-28

    申请号:US419139

    申请日:1989-10-10

    IPC分类号: C22C16/00 G21C3/07 G21C3/34

    摘要: A zirconium alloy for use in spacer grids for nuclear reactor fuel claddings, which consists essentially of, on a weight percent basis,2.5 to 10% Nb,0.01 to 1.5% of one or more components selected from the group consisting of Y and rare earth elements and oxides thereof,0.05 to 1% of one or more optional element selected from the group consisting of Fe, Cr, Mo and V, andthe remainder Zr and incidental impurities.

    摘要翻译: 一种用于核反应堆燃料包层的间隔栅格的锆合金,其基本上由以重量百分数计,2.5至10%的Nb,0.01至1.5%的选自Y和稀土的一种或多种组分 元素和氧化物,0.05-1%选自Fe,Cr,Mo和V的一种或多种任选元素,余量为Zr和附带杂质。

    Enclosing a gas in a nuclear reactor fuel rod
    7.
    发明授权
    Enclosing a gas in a nuclear reactor fuel rod 失效
    在核反应堆燃料棒中包围气体

    公开(公告)号:US4570051A

    公开(公告)日:1986-02-11

    申请号:US449108

    申请日:1982-12-13

    申请人: Nobuo Miwa

    发明人: Nobuo Miwa

    CPC分类号: G21C21/00 B23K9/028

    摘要: A method and system for enclosing a gas at a preselected pressure in a nuclear reactor fuel rod having two ends open to its interior. Hermetically enclose each end in a separate airtight chamber. Introduce the gas into the first chamber and open the second chamber to purge the fuel rod interior and both chambers of residual atmosphere. After purging close the open second chamber and determine the gas pressure in the fuel rod interior. When the pressure reaches the preselected value, hermetically seal each fuel rod end while in its respective chamber. After sealing, remove the fuel rod from the chambers.

    摘要翻译: 一种用于在预反应的压力下封闭气体的方法和系统,该核反应堆燃料棒的两端开放到其内部。 将每一端密封在一个独立的气密室中。 将气体引入第一个室并打开第二个室,以清除燃料棒内部和两个室的残留气氛。 吹扫关闭开放的第二室并确定燃料棒内部的气体压力。 当压力达到预选值时,在其各自的室内气密地密封每个燃料棒端。 密封后,将燃料棒从室中取出。

    Process for manufacturing uranium dioxide powder
    9.
    发明授权
    Process for manufacturing uranium dioxide powder 失效
    制造二氧化铀粉的工艺

    公开(公告)号:US4505882A

    公开(公告)日:1985-03-19

    申请号:US478372

    申请日:1983-03-24

    IPC分类号: B01J2/00 C01G43/025 G21C3/62

    摘要: A process for manufacturing uranium dioxide powder which comprises forming fine uranium dioxide powder having a high sinterability and coarse uranium dioxide powder having a low sinterability continuously in one process by changing periodically the precipitation condition of the ammonium diuranate under the same condition of calcining and reducing of the ammonium diuranate. The thus obtained mixture of these uranium dioxide powders is suitable for uranium dioxide pellet which is a fuel of nuclear power reactor.

    摘要翻译: 一种二氧化钛粉末的制造方法,其特征在于,在相同的煅烧条件下,通过在相同的条件下周期性地变化所述二硫酸铵的沉淀条件,在一个方法中连续地形成具有高烧结性的微细二氧化铀粉末和粗二氧化铀粉末, 十二烷酸铵。 由此获得的这些二氧化铀粉末的混合物适用于作为核动力反应堆燃料的二氧化铀颗粒。

    Fuel rod for light water reactor and method for manufacturing the same
    10.
    发明授权
    Fuel rod for light water reactor and method for manufacturing the same 失效
    轻水反应堆用燃料棒及其制造方法

    公开(公告)号:US6014418A

    公开(公告)日:2000-01-11

    申请号:US908694

    申请日:1997-08-08

    IPC分类号: G21C3/06 G21C3/07 G21C21/02

    摘要: A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs comprising a zirconium alloy and closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Grain boundaries in each heat affected zone of the cladding tube, which are adjacent to a bead formed by TIG welding, have structural compositions including 4 to 30% by weight of Nb, and 0.9 to 20% by weight of Fe.

    摘要翻译: 一种用于轻水反应器的燃料棒包括一个包层管,它包括一种锆合金,其组成包括Nb为0.6-2.0%,Sn为0.5-1.5%,Fe为0.05-0.3%,以及 余量为Zr和杂质; 包裹在包壳管内的氧化铀燃料颗粒; 以及包括锆合金并封闭包层管的两端的端塞。 包层管通过TIG焊接与端塞密封。 与通过TIG焊接形成的焊道相邻的包覆管的每个受热影响区域中的晶界具有包含4至30重量%的Nb和0.9至20重量%的Fe的结构组成。