Process for improving corrosion resistance of zirconium or zirconium
alloy barrier cladding
    42.
    发明授权
    Process for improving corrosion resistance of zirconium or zirconium alloy barrier cladding 失效
    提高锆或锆合金屏障包层耐蚀性的工艺

    公开(公告)号:US5417780A

    公开(公告)日:1995-05-23

    申请号:US142034

    申请日:1993-10-28

    Abstract: A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.

    Abstract translation: 一种用于制造复合包层的方法,其包括冶金结合在锆合金管的内表面上的锆的中等纯度金属屏障,其提高耐腐蚀性。 衬垫的改善的耐腐蚀性是通过合适的热处理Zircaloy-锆复合材料包层来实现的,以允许合金元素,特别是Fe和Ni从Zircaloy扩散到锆中,特别是锆衬里的内表面 。 该扩散退火减少了锆衬垫快速氧化的不期望的趋势。

    Heat treatment of Alloy 718 for improved stress corrosion cracking
resistance
    43.
    发明授权
    Heat treatment of Alloy 718 for improved stress corrosion cracking resistance 失效
    718合金的热处理,提高应力腐蚀开裂性能

    公开(公告)号:US5244515A

    公开(公告)日:1993-09-14

    申请号:US845126

    申请日:1992-03-03

    Inventor: Marie T. Miglin

    Abstract: A method of increasing intergranular stress corrosion cracking resistance of Alloy 718 in water reactor environments is described where the alloy is heat treated at a high solution annealing temperature to dissolve grain boundary precipitates formed during thermomechanical processing. A water quenching step is advantageously employed following the high solution annealing. The alloy is then aged at two separate temperatures and finally air cooled to room temperature.

    Abstract translation: 描述了在水溶液环境中增加合金718的晶间应力腐蚀开裂性的方法,其中合金在高固溶退火温度下热处理以溶解在热机械加工过程中形成的晶界析出物。 在高固溶退火之后有利地采用水淬步骤。 然后将合金在两个独立的温度下老化,最后空气冷却至室温。

    Coating a nuclear fuel with a burnable poison
    47.
    发明授权
    Coating a nuclear fuel with a burnable poison 失效
    涂上可燃毒物的核燃料

    公开(公告)号:US4587088A

    公开(公告)日:1986-05-06

    申请号:US526712

    申请日:1983-08-26

    Abstract: A method for coating a nuclear fuel with a burnable poison and a burnable poison coated nuclear fuel made by the method. The nuclear fuel is surface cleaned, and then a burnable poison layer is sputtered thereon. A sputtering deposition rate is picked that preferably will heat the nuclear fuel surface between 200.degree. C. and 600.degree. C. For deposition rates that result in heating the nuclear fuel surface to less than 200.degree. C., external heat is applied to heat the nuclear fuel surface between 200.degree. C. and 600.degree. C. To make the burnable poison layer less hygroscopic, an overcoat layer of a hydrophobic material is sputtered on the burnable poison layer.

    Abstract translation: 一种通过该方法制备的具有可燃毒物和可燃烧毒物的核燃料的核燃料的涂覆方法。 核燃料被表面清洁,然后在其上溅射可燃毒物层。 选择溅射沉积速率,优选将核燃料表面加热到200℃至600℃。对于导致将核燃料表面加热到小于200℃的沉积速率,施加外部热量以加热 核燃料表面在200℃至600℃之间。为了使可燃毒物层吸湿较少,疏水材料的外涂层溅射在可燃毒物层上。

    LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields
    50.
    发明申请
    LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields 有权
    LWR流道在暴露于中子辐射和腐蚀场的同时降低了对变形的敏感性和控制叶片的干扰

    公开(公告)号:US20070153963A1

    公开(公告)日:2007-07-05

    申请号:US11320477

    申请日:2005-12-29

    Abstract: A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.

    Abstract translation: 适用于形成反应器组分的锆合金,其在轻水反应器(LWR),例如沸水反应器(BWR)的操作期间表现出减少的照射生长和改善的耐腐蚀性。 在反应器的操作期间,反应器部件将暴露于足以引起或加速反应堆堆芯内辐射的合金表面的腐蚀的强烈且常常不对称的辐射场。 由公开的锆合金制造的反应器部件也将倾向于在部件制造期间显示出对冷加工的改善的公差,从而通过减少或消除随后的热处理(例如退火)来简化这些部件的制造,而不会不适当地降低 成品组件的性能。

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