Element immersed in coolant of nuclear reactor

    公开(公告)号:US4606109A

    公开(公告)日:1986-08-19

    申请号:US570487

    申请日:1984-01-13

    Applicant: Albert Weiss

    Inventor: Albert Weiss

    Abstract: The zirconium cladding of a coolant-displacement rod of a nuclear reactor is precollapsed in the zirconium oxide stack of pellets which supports the cladding. Current is conducted through the cladding in an atmosphere at reduced pressure containing residual oxygen, to heat the cladding to a temperature at which its yield strength is reduced. Then, while the rod remains at this temperature, it is subjected to isostatic pressure which collapses the cladding uniformly. The formation, by reason of exposure to neutron flux, of a long unsupported gap in the cladding which might be collapsed under the pressure of the coolant is precluded. In addition, the rod retains its symmetry. The outer surface of the cladding is oxidized, facilitating the movement of the rod into its thimbles of the core and improving the resistances of the cladding to reaction with the coolant.

    Heat-treated zirconium alloy product
    115.
    发明授权
    Heat-treated zirconium alloy product 失效
    热处理锆合金产品

    公开(公告)号:US4226647A

    公开(公告)日:1980-10-07

    申请号:US914829

    申请日:1978-06-12

    Abstract: High tensile strength, creep and corrosion resistant zirconium alloys containing 7.0-10.0 wt % aluminum, 0-3 wt % in total of one or more elements selected from the group consisting of magnesium, tin, chromium, iron, carbon, silicon, yttrium, niobium, molybdenum and beryllium, the balance zirconium and incidental impurities, are produced by annealing cast alloys at a temperature below about 992.degree. C. for a period of time sufficient to produce alloys having a substantially continuous matrix of the ordered intermetallic compound Zr.sub.3 Al. The alloys may initially be hot worked at temperatures about 1000.degree. C., while in the .beta.Zr-Zr.sub.2 Al two phase region, prior to annealing. Preferred alloys contain 7.5-9.5 wt % aluminum, the balance zirconium and incidental impurities.

    Abstract translation: 含有7.0-10.0重量%铝的高抗拉强度,蠕变和耐腐蚀的锆合金,0-3重量%的总计选自镁,锡,铬,铁,碳,硅,钇, 铌,钼和铍,余量为锆和附带杂质,通过在低于约992℃的温度下退火铸造合金制造足够长的时间,足以产生具有基本连续的有序金属间化合物Zr 3 Al基体的合金。 该合金最初可以在退火前在约1000℃的温度下热处理,而在βZr-Zr2Al两相区域。 优选的合金含有7.5-9.5重量%的铝,余量为锆和附带的杂质。

    Preparation of zirconium alloys
    116.
    发明授权
    Preparation of zirconium alloys 失效
    锆合金的制备

    公开(公告)号:US4094706A

    公开(公告)日:1978-06-13

    申请号:US711744

    申请日:1976-08-04

    Abstract: High tensile strength, creep and corrosion resistant zirconium alloys containing 7.0-10.0 wt% aluminum, 0-3 wt% in total of one or more elements selected from the group consisting of magnesium, tin, chromium, iron, carbon, silicon, yttrium, niobium, molybdenum and beryllium, the balance zirconium and incidental impurities, are produced by annealing cast alloys at a temperature below about 992.degree. C for a period of time sufficient to produce alloys having a substantially continuous matrix of the ordered intermetallic compound Zr.sub.3 Al. The alloys may initially be hot worked at temperatures above about 1000.degree. C, while in the .beta.Zr-Zr.sub.2 Al two phase region, prior to annealing. Preferred alloys contain 7.5-9.5% aluminum, the balance zirconium and incidental impurities.

    Abstract translation: 含有7.0-10.0重量%铝的高抗拉强度,蠕变和耐腐蚀的锆合金,0-3重量%的总计选自镁,锡,铬,铁,碳,硅,钇, 铌,钼和铍,余量为锆和杂质,是通过在低于约992℃的温度下退火铸造合金一段足以产生具有基本上连续的有序金属间化合物Zr 3 Al基体的合金的时间产生的。 该合金最初可以在高于约1000℃的温度下热处理,而在βZr-Zr2Al两相区域中,退火之前。 优选的合金含有7.5-9.5%的铝,余量为锆和附带的杂质。

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