Fuel rod for light water reactor and method for manufacturing the same
    5.
    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。

    Method for making Zr alloy nuclear reactor fuel cladding having
excellent corrosion resistance and creep properties
    7.
    发明授权
    Method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties 有权
    制造Zr合金核反应堆燃料包层的方法具有优异的耐腐蚀性和蠕变性

    公开(公告)号:US6125161A

    公开(公告)日:2000-09-26

    申请号:US397094

    申请日:1999-09-16

    摘要: The invention provides a method for making Zr alloy nuclear reactor fuel cladding having excellent corrosion resistance and creep properties. The method includes performing hot forging, solution heat treatment, hot extruding, and repeated cycles of annealing and cold rolling of a Zr alloy including, by weight, 0.2 to 1.7% Sn, 0.18 to 0.6% Fe, 0.07 to 0.4% Cr and 0.05 to 1.0% Nb, with the remainder being Zr and incidental impurities, and the incidental nitrogen impurity content being 60 ppm or less, and then performing final stress relief annealing thereon. The annealing is performed at a temperature of 550.degree. C. to 850.degree. C. for 1 to 4 hours such that the accumulated annealing parameter .SIGMA.Ai=.SIGMA.ti.multidot.exp(-40,000/Ti) satisfies relationships -20.ltoreq.log.SIGMA.Ai.ltoreq.-15, and -18-10.multidot.X.sub.Nb .ltoreq.log.SIGMA.Ai.ltoreq.-15-3.75.multidot.(X.sub.Nb -0.2), wherein Ai represents the annealing parameter for the i-th annealing, ti represents the annealing time (hours) for the i-th annealing, Ti represents the annealing temperature (K) for the i-th annealing, and X.sub.Nb represents the Nb concentration (wt %).

    摘要翻译: 本发明提供了一种制造具有优异的耐腐蚀性和蠕变性的Zr合金核反应堆燃料包覆的方法。 该方法包括进行热锻,固溶热处理,热挤压以及Zr合金的退火和冷轧的重复循环,所述Zr合金的重量为0.2〜1.7%的Sn,0.18〜0.6%的Fe,0.07〜0.4%的Cr和0.05 至1.0%的Nb,其余为Zr和杂质,偶氮含量为60ppm以下,然后对其进行最终的应力消除退火。 退火在550℃至850℃的温度下进行1至4小时,使得累积退火参数SIGMA Ai = SIGMA tixexp(-40,000 / Ti)满足关系-20