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1.发明授权
公开(公告)号：US5469481A
公开(公告)日：1995-11-21
申请号：US215456
申请日：1994-03-21
IPC分类号： B21C37/06 , C22F1/18 , G21C3/06 , G21C3/18 , G21C3/20 , G21C21/02 , G21C21/10 , G21D1/00 , G21C3/00
CPC分类号： G21C3/20 , C22F1/186 , G21C21/02 , G21C21/10 , G21C3/06 , G21C3/18 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2002/303 , G21Y2004/10 , G21Y2004/20 , G21Y2004/40 , Y02E30/40
摘要： A method is provided for forming a three-layer cladding tube having an outer substrate, a zirconium barrier layer, and an inner liner having alloying elements, in which the zirconium barrier layer (located between an outer substrate and inner liner) is at least partially alloyed with alloying elements that impart resistance to corrosion. The barrier layer has a diffusion layer extending from its inner surface (facing the fuel) to the barrier layer's interior (the interior being defined between the barrier layer's inner and outer surfaces). At the interior edge of the diffusion layer, there will be substantially no alloying elements beyond those normally present in zirconium. The methods of forming such structure include a diffusion anneal of a three-layer cladding in the range of 650.degree.-1000.degree. C. for times between about 1 minute and 20 hours. This anneal drives some of the alloying elements from the inner liner into the zirconium barrier layer to form the diffusion layer. The exact time and temperature depends upon the fabrication stage at which the heat treatment occurs.
摘要翻译： 提供了一种用于形成具有外基材，锆阻挡层和具有合金元素的内衬层的三层包覆管的方法，其中，所述锆阻挡层（位于外基材和内衬层之间）至少部分地 与赋予耐腐蚀性的合金元素合金化。 阻挡层具有从其内表面（面向燃料）延伸到阻挡层内部（内部限定在阻挡层的内表面和外表面之间）的扩散层。 在扩散层的内部边缘处，基本上不存在通常存在于锆中的合金元素。 形成这种结构的方法包括在约1分-20小时之间的650℃-1000℃范围内的三层包层的扩散退火。 该退火将一些合金元素从内衬驱动到锆阻挡层中以形成扩散层。 精确的时间和温度取决于发生热处理的制造阶段。
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2.发明授权
公开(公告)号：US5578145A
公开(公告)日：1996-11-26
申请号：US368832
申请日：1994-12-14
申请人： Ronald B. Adamson , Daniel R. Lutz
发明人： Ronald B. Adamson , Daniel R. Lutz
CPC分类号： G21C3/20 , G21Y2002/103 , G21Y2004/201 , Y02E30/40 , Y10T428/12458 , Y10T428/12806
摘要： 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.
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公开(公告)号：US5524032A
公开(公告)日：1996-06-04
申请号：US215458
申请日：1994-03-21
CPC分类号： G21C3/06 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2004/10 , G21Y2004/20 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A cladding tube having a cross-section and including (1) a zirconium alloy outer circumferential substrate having an inner surface and having one or more alloying elements, (2) a zirconium barrier layer bonded to the inner surface of the outer circumferential substrate and being alloyed with the one or more alloying elements, and (3) a zirconium alloy inner circumferential liner bonded to the inner surface of the zirconium barrier layer. The barrier layer will have a concentration profile including a diffusion layer extending from the barrier layer's inner surface (facing nuclear fuel) to the barrier layer's interior (between the barrier layer's inner and outer surfaces). At the interior edge of the diffusion layer, there will be substantially no alloying elements. At the outer edge of the diffusion layer (the barrier layer's inner surface), the maximum concentration of alloying elements will occur.
摘要翻译： 一种具有横截面的包层管，包括（1）具有内表面并具有一个或多个合金元素的锆合金外周基材，（2）结合到外周基材的内表面上的锆阻挡层，并且 与一种或多种合金元素合金化，和（3）结合到锆阻挡层的内表面的锆合金内周衬垫。 阻挡层将具有包括从阻挡层的内表面（面向核燃料）延伸到阻挡层内部（阻挡层的内表面和外表面之间）的扩散层的浓度分布。 在扩散层的内部边缘处，基本上不存在合金元素。 在扩散层的外缘（阻挡层的内表面）处，将发生合金元素的最大浓度。
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4.发明授权
公开(公告)号：US5417780A
公开(公告)日：1995-05-23
申请号：US142034
申请日：1993-10-28
申请人： Ronald B. Adamson , Daniel R. Lutz
发明人： Ronald B. Adamson , Daniel R. Lutz
CPC分类号： G21C3/20 , G21Y2002/103 , G21Y2004/201 , Y02E30/40 , Y10T428/12458 , Y10T428/12806
摘要： 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.
摘要翻译： 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。
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5.发明申请Nuclear reactor components including material layers to reduce enhanced corrosion on zirconium alloys used in fuel assemblies and methods thereof 审中-公开核反应堆组件包括材料层，以减少用于燃料组件中的锆合金的增强的腐蚀及其方法公开(公告)号：US20100014624A1
公开(公告)日：2010-01-21
申请号：US12219212
申请日：2008-07-17
申请人： Daniel R. Lutz , Young Jin Kim , Yang-Pi Lin
发明人： Daniel R. Lutz , Young Jin Kim , Yang-Pi Lin
CPC分类号： G21C17/0225 , G21C3/356 , G21C21/02
摘要： Example embodiments are directed to providing a thin, adherent coating on the surfaces of nuclear reactor components, which are known to cause increased corrosion on adjacent zirconium alloy structures, and methods of reducing the increased corrosion. Example embodiments include coatings being structurally bonded to components such that the difference in the corrosion potential between a coated component and a zirconium alloy component is less than that between a component without the coating and the zirconium alloy component.
摘要翻译： 示例性实施例涉及在核反应堆组件的表面上提供薄的粘附涂层，这已知会对相邻的锆合金结构造成增加的腐蚀，以及减少增加的腐蚀的方法。 示例性实施方案包括在结构上结合到组分的涂层，使得涂覆组分和锆合金组分之间的腐蚀电位差异小于没有涂层的组分和锆合金组分之间的腐蚀电位差。
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公开(公告)号：US09637809B2
公开(公告)日：2017-05-02
申请号：US12624845
申请日：2009-11-24
申请人： Yang-Pi Lin , David W. White , Daniel R. Lutz
发明人： Yang-Pi Lin , David W. White , Daniel R. Lutz
IPC分类号： C22C16/00
CPC分类号： C22C16/00
摘要： An alloy according to example embodiments of the present invention may include zirconium, tin, iron, chromium, and nickel, with a majority of the alloy being zirconium. The composition of the alloy may be about 0.85-2.00% tin by weight, about 0.15-0.30% iron by weight, about 0.40-0.75% chromium by weight, and less than 0.01% nickel by weight. The alloy may further include 0.004-0.020% silicon by weight, 0.004-0.020% carbon by weight, and/or 0.05-0.20% oxygen by weight. Accordingly, the alloy exhibits reduced hydrogen absorption and improved corrosion resistance and may be used to form a fuel assembly component.
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7.发明授权公开(公告)号：US09139895B2
公开(公告)日：2015-09-22
申请号：US10935157
申请日：2004-09-08
申请人： David White , Daniel R. Lutz , Yang-Pi Lin , John Schardt , Gerald Potts
发明人： David White , Daniel R. Lutz , Yang-Pi Lin , John Schardt , Gerald Potts
摘要： Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about 0.31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.
摘要翻译： 本文公开了锆基合金和从这种在侵蚀性冷却剂组合物中表现出改进的耐腐蚀性的合金制造核反应堆部件，特别是燃料包壳管的方法。 制造步骤包括在管的外部区域的后期和后处理。 锆基合金将包括约1.30至1.60重量％的锡; 约0.06至0.15重量％的铬; 约0.16至0.24重量％的铁，以及0.05至0.08重量％的镍，其中铁，铬和镍的总含量高于合金的约0.31重量％，其特征在于具有平均尺寸的第二相沉淀 通常小于约40nm。 最终完成的包层将具有小于约0.50μmRa的表面粗糙度，优选小于约0.10μmRa的表面粗糙度。
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8.发明授权公开(公告)号：US08043448B2
公开(公告)日：2011-10-25
申请号：US10935156
申请日：2004-09-08
申请人： David White , Daniel R. Lutz , Yang-Pi Lin , John Schardt , Gerald Potts , Robert Elkins , Hiroaki Kagami , Hideyuki Mukai
发明人： David White , Daniel R. Lutz , Yang-Pi Lin , John Schardt , Gerald Potts , Robert Elkins , Hiroaki Kagami , Hideyuki Mukai
IPC分类号： C22F1/18
摘要： Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.
摘要翻译： 这里公开的是锆基合金，其可以被制造成形成核反应堆组分，特别是燃料包覆管，其表现出足够的耐腐蚀性和氢吸收特性，而不需要晚期α+和bgr; 或＆bgr; - 修复过程。 锆基合金将包括约1.30-1.60重量％的锡; 0.0975-0.15重量％铬; 0.16-0.24重量％铁; 和至多约0.08重量％的镍，其中铁，铬和镍的总含量占合金的至少约0.3175重量％。 所得组分将表现出具有约50-100nm的平均沉淀尺寸的表面区域和小于约2×10-19小时的Sigma A，其中工件加工通常限于低于680℃的温度用于挤出 并且对于所有其他操作而言低于625℃，从而简化了核反应堆部件的制造，同时提供了与常规合金相当的耐腐蚀性。
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公开(公告)号：US20110123388A1
公开(公告)日：2011-05-26
申请号：US12624845
申请日：2009-11-24
申请人： Yang-Pi Lin , David W. White , Daniel R. Lutz
发明人： Yang-Pi Lin , David W. White , Daniel R. Lutz
IPC分类号： C22C16/00
CPC分类号： C22C16/00
摘要： An alloy according to example embodiments of the present invention may include zirconium, tin, iron, chromium, and nickel, with a majority of the alloy being zirconium. The composition of the alloy may be about 0.85-2.00% tin by weight, about 0.15-0.30% iron by weight, about 0.40-0.75% chromium by weight, and less than 0.01% nickel by weight. The alloy may further include 0.004-0.020% silicon by weight, 0.004-0.020% carbon by weight, and/or 0.05-0.20% oxygen by weight. Accordingly, the alloy exhibits reduced hydrogen absorption and improved corrosion resistance and may be used to farm a fuel assembly component.
摘要翻译： 根据本发明的示例性实施方案的合金可以包括锆，锡，铁，铬和镍，大部分合金是锆。 合金的组成可以是约0.85-2.00重量％的锡，约0.15-0.30重量％的铁，约0.40-0.75重量％的铬和小于0.01重量％的镍。 该合金还可以包括0.004-0.020重量％的硅，0.004-0.020重量％的碳，和/或0.05-0.20重量％的氧。 因此，合金表现出降低的氢吸收和改善的耐腐蚀性，并且可用于养殖燃料组件部件。
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