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    • 6. 发明授权
    • Method for making Zr alloy nuclear reactor fuel cladding having
excellent corrosion resistance and creep properties
    • 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
    • US6125161A
    • 2000-09-26
    • US397094
    • 1999-09-16
    • Takeshi IsobeYoshitaka Suda
    • Takeshi IsobeYoshitaka Suda
    • C22C16/00C22F1/00C22F1/18G21C3/06G21C3/07
    • G21C3/07G21Y2002/103G21Y2002/104G21Y2004/10G21Y2004/40Y02E30/40
    • 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 %).
    • 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