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    • 1. 发明授权
    • Method for determining corrosion susceptibility of nuclear fuel cladding
to nodular corrosion
    • 确定核燃料包层对结核腐蚀的腐蚀敏感性的方法
    • US5991352A
    • 1999-11-23
    • US50214
    • 1998-03-30
    • Dale Frederick Taylor
    • Dale Frederick Taylor
    • C22F1/18G21C17/00G21C19/00
    • G21C17/00C22F1/186Y10S436/908
    • A method for determining the susceptibility of a sample of Zircaloy alloy to nodular corrosion. A specimen of such Zircaloy sample is annealed at a temperature within a temperature range bounded at its upper limit by the temperature T.sub.c being the temperature at equilibrium wherein sufficient solute would exist in the (.alpha.-matrix of the particular zircaloy to resist nodular corrosion, and bounded by a lower temperature, such temperature being the temperature of the (.alpha.+precipitate)/(.alpha.+.beta.+precipitate) transus for the particular Zircaloy sample. For Zircaloy-2, such temperature range is from approximately 825.degree. C. to 841.degree. C. The specimen is maintained at such selected temperature within such temperature range for a measured period, and subsequently exposed to steam at a fixed temperature and pressure for a fixed time. If nodular corrosion does not appear the above steps are repeated, but on each different specimen increasing the measured time period until a last measured time period is obtained when nodular corrosion first appears on a specimen. The length of the last measured time period is used as an indicator of the sample's resistance to nodular corrosion, and thus conversely its susceptibility to nodular corrosion.
    • 一种确定Zircaloy合金样品对结节腐蚀的敏感性的方法。 这种Zircaloy样品的样品在其上限温度范围内的温度下退火,其温度Tc为平衡温度,其中足够的溶质将存在于特定的氧化锆中的α-基质以抵抗结核腐蚀,以及 对于Zircaloy-2来说,这个温度是(α+沉淀物)/(α+β+沉淀物)/(α+β+沉淀物)转化温度,温度范围是从大约825℃到841℃ 将样品在这样的温度范围内保持一定的时间,然后在固定温度和压力下暴露于蒸汽一段固定的时间,如果没有出现结节腐蚀,则重复上述步骤,但是 每个不同的样品增加测量的时间段,直到最终测量的时间段在样品上首次出现结节腐蚀时,获得长度 最后测量的时间段用作样品对结节腐蚀的抗性的指标,因此反过来也是对结节腐蚀的敏感性。
    • 2. 发明授权
    • Corrosion resistant zirconium alloy for extended-life fuel cladding
    • 耐腐蚀锆合金,用于延长寿命的燃料包层
    • US5699396A
    • 1997-12-16
    • US342965
    • 1994-11-21
    • Dale Frederick Taylor
    • Dale Frederick Taylor
    • C22C16/00G21C3/07G21C3/20G21C3/00
    • C22C16/00G21C3/07G21Y2002/103G21Y2004/10Y02E30/40
    • A zirconium-based alloy with a reduced ahoy content is described that has resistance to both uniform and nodular corrosion comparable to present zirconium-based alloy compositions, such as Zircaloy-2. The alloy represents in essence a modified or diluted Zircaloy-2 or Zircaloy-4. The alloys of this invention are also expected to have improved uniform corrosion resistance at under high burn-up conditions The alloy comprises 0.05-0.09 weight percent of iron, 0.03-0.05 weight percent of chromium, 0.02-0.04 weight percent of nickel, 1.2-1.7 weight percent of tin and 0-0.15 weight percent oxygen, with a balance of zirconium. The iron chromium and nickel alloying elements form precipitates in the alloy matrix. The alloy is suitable for use as a cladding material for a fuel element housing fissionable nuclear materials in water cooled nuclear fission reactor. These alloys can also be formed with a reduced nitrogen content of no more than 20 parts per million nitrogen by weight in order to provide enhanced resistance to nodular corrosion.
    • 描述了具有降低的杂质含量的锆基合金,其具有与现有的锆基合金组合物(例如Zircaloy-2)相当的均匀和结节腐蚀的抗性。 该合金本质上是改性或稀释的Zircaloy-2或Zircaloy-4。 还预期本发明的合金在高燃烧条件下具有改进的均匀耐腐蚀性。该合金包含0.05-0.09重量%的铁,0.03-0.05重量%的铬,0.02-0.04重量%的镍, 1.7重量%的锡和0-0.15重量%的氧,余量为锆。 铁铬和镍合金元素在合金基质中形成析出物。 该合金适用于水冷核裂变反应堆中用于容纳可裂变核材料的燃料元件的包层材料。 这些合金也可以以不超过20重量份的氮含量为20重量%的氮含量形成,以提供对结核腐蚀的增强的抗性。
    • 3. 发明授权
    • Protective coarsening anneal for zirconium alloys
    • 锆合金的保护性粗化退火
    • US06355118B1
    • 2002-03-12
    • US09638493
    • 2000-08-15
    • Dale Frederick Taylor
    • Dale Frederick Taylor
    • C22C1600
    • C22F1/186
    • A method for increasing the resistance of zirconium alloy tubing to nodular corrosion by applying a protective anneal at a temperature within a clearly defined temperature range. Also, a zirconium alloy tubing having such protective anneal is disclosed. The protective anneal comprises heating exposed surfaces of zirconium tubing to a temperature range bounded at its lower limit by the temperature Tc, Tc being the temperature which at equilibrium conditions a critical concentration of solute exists in &agr;-matrices of the zirconium alloy to resist nodular corrosion, and bounded at its upper limit by the maximum temperature at which precipitates exist in association with the &agr; and &bgr; matrices in the particular zirconium alloy. In respect of Zircalloy-2 containing zirconium and the following metals by weight, namely 1.2-1.7% tin, 0.13-0.20% iron, 0.06-0.15% chromium, and 0.05-0.08% nickel, the lower temperature limit Tc is approximately 840 C and the upper limit is approximately 855 C.
    • 一种通过在明确定义的温度范围内的温度下施加保护性退火来增加锆合金管对结核腐蚀的阻力的方法。 此外,公开了具有这种保护性退火的锆合金管。 保护性退火包括将锆管的暴露表面加热到其下限处的温度范围,温度Tc,Tc是在平衡条件下溶质临界浓度存在于锆合金的α-基质中以抵抗结节腐蚀的温度 ,并且在其上限处与特定锆合金中的α和β基体相关联的析出物存在的最高温度。 对于含锆锆合金和以下重金属的金属,即1.2-1.7%的锡,0.13-0.20%的铁,0.06-0.15%的铬和0.05-0.08%的镍,下限温度Tc约为840℃ 上限约为855℃。
    • 4. 发明授权
    • Protective coarsening anneal for zirconium alloys
    • 锆合金的保护性粗化退火
    • US6126762A
    • 2000-10-03
    • US186013
    • 1998-11-04
    • Dale Frederick Taylor
    • Dale Frederick Taylor
    • C22F1/00C22F1/18
    • C22F1/186
    • A method for increasing the resistance of zirconium alloy tubing to nodular corrosion by applying a protective anneal at a temperature within a clearly defined temperature range. Also, a zirconium alloy tubing having such protective anneal is disclosed. The protective anneal comprises heating exposed surfaces of zirconium tubing to a temperature range bounded at its lower limit by the temperature T.sub.c, T.sub.c being the temperature which at equilibrium conditions a critical concentration of solute exists in .alpha.-matrices of the zirconium alloy to resist nodular corrosion, and bounded at its upper limit by the maximum temperature at which precipitates exist in association with the .alpha. and .beta. matrices in the particular zirconium alloy. In respect of Zircalloy-2 containing zirconium and the following metals by weight, namely 1.2-1.7% tin, 0.13-0.20% iron, 0.06-0.15% chromium, and 0.05-0.08% nickel, the lower temperature limit T.sub.c is approximately 840 C and the upper limit is approximately 855 C.
    • 一种通过在明确定义的温度范围内的温度下施加保护性退火来增加锆合金管对结核腐蚀的阻力的方法。 此外,公开了具有这种保护性退火的锆合金管。 保护性退火包括将锆管的暴露表面加热到其下限处的温度范围,温度Tc,Tc是在平衡条件下溶质的临界浓度存在于锆合金的α-基质中以抵抗结节腐蚀的温度 ,并且在其上限处与特定锆合金中的α和β基体相关联的析出物存在的最高温度。 对于含锆锆合金和以下重金属的金属,即1.2-1.7%的锡,0.13-0.20%的铁,0.06-0.15%的铬和0.05-0.08%的镍,下限温度Tc约为840℃ 上限约为855℃。