公开(公告)号：US20160005499A1

公开(公告)日：2016-01-07

申请号：US14323506

申请日：2014-07-03

Applicant: Yang-Pi LIN ,  Young Jin KIM ,  David William WHITE ,  Garrett Scott NAVE ,  Patricia P. MCCUMBEE

Inventor： Yang-Pi LIN ,  Young Jin KIM ,  David William WHITE ,  Garrett Scott NAVE ,  Patricia P. MCCUMBEE

IPC: G21C19/00 ,  B05D3/02 ,  B05D3/04 ,  G21C21/00 ,  B05D1/18

CPC classification number: G21C19/00 ,  B05D1/18 ,  B05D3/0254 ,  B05D3/0406 ,  C09D1/00 ,  C09D7/61 ,  C23C24/082 ,  G21C17/0225 ,  G21C21/00 ,  G21C21/18

Abstract: A method of coating a nuclear reactor component includes introducing the nuclear reactor component into a colloidal solution at a first rate to obtain an immersed component. The colloidal solution is a non-crosslinked mixture including a dispersed phase within a dispersion medium. The dispersed phase may include n-type metal oxide particles. The method additionally includes removing the immersed component from the colloidal solution at a second rate to obtain a wet component. The method also includes drying the wet component to obtain a dried component. The method further includes baking the dried component to obtain a coated component. Accordingly, the nuclear reactor component is provided with a protective layer that reduces or prevents the occurrence of corrosion.

Abstract translation: 涂布核反应堆组件的方法包括以一次速率将核反应堆组分引入胶体溶液中以获得浸没的组分。 胶体溶液是包含分散介质内的分散相的非交联混合物。 分散相可以包括n型金属氧化物颗粒。 该方法另外包括以第二速率从胶体溶液中除去浸没的组分以获得湿组分。 该方法还包括干燥湿组分以获得干燥组分。 该方法还包括烘烤干燥的组分以获得涂布的组分。 因此，核反应堆部件设置有减少或防止腐蚀发生的保护层。

公开(公告)号：US08792607B2

公开(公告)日：2014-07-29

申请号：US12250699

申请日：2008-10-14

Applicant: Young Jin Kim ,  Dennis Michael Gray ,  David William White ,  Yang-Pi Lin ,  Todd Charles Curtis ,  Charles Beaty Patterson

Inventor： Young Jin Kim ,  Dennis Michael Gray ,  David William White ,  Yang-Pi Lin ,  Todd Charles Curtis ,  Charles Beaty Patterson

IPC: G21C9/00

CPC classification number: G21C3/20 ,  G21C3/07 ,  G21C3/356 ,  G21C17/0225 ,  G21C21/02 ,  Y02E30/40

Abstract: There is provided a fuel rod assembly comprising a first component of a zirconium-based material. The first component is in contact with or is located adjacent to a second component of a material different from the zirconium-based material, e.g. a nickel-based or iron-based alloy. A coating is disposed on an outer surface of the first component, which is effective to reduce an electrochemical corrosion potential difference between the first component and the second component relative to an electrochemical corrosion potential difference between the first component and the second component without the coating.

Abstract translation: 提供了一种包括锆基材料的第一组分的燃料棒组件。 第一组分与不同于锆基材料的材料的第二组分接触或位于其邻近位置。 镍基或铁基合金。 涂层设置在第一部件的外表面上，其有效地减少第一部件和第二部件之间的电化学腐蚀电位差，相对于第一部件和第二部件之间的电化学腐蚀电位差而没有涂覆。

公开(公告)号：US08116422B2

公开(公告)日：2012-02-14

申请号：US11320477

申请日：2005-12-29

Applicant: Daniel Reese Lutz ,  Gerald Allen Potts ,  Yang-Pi Lin ,  Sheikh Tahir Mahmood ,  Mark Andrew Dubecky ,  David William White ,  John Schardt

Inventor： Daniel Reese Lutz ,  Gerald Allen Potts ,  Yang-Pi Lin ,  Sheikh Tahir Mahmood ,  Mark Andrew Dubecky ,  David William White ,  John Schardt

IPC: G21C9/00 ,  G21C7/10

CPC classification number: G21C3/07 ,  G21C3/324 ,  G21Y2002/203 ,  G21Y2002/207 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

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。

公开(公告)号：US20090022259A1

公开(公告)日：2009-01-22

申请号：US11780537

申请日：2007-07-20

Applicant: Dennis Michael Gray ,  David William White ,  Peter Louis Andresen ,  Young Jin Kim ,  Yang-Pi Lin ,  Todd Charles Curtis ,  Charles Beaty Patterson

Inventor： Dennis Michael Gray ,  David William White ,  Peter Louis Andresen ,  Young Jin Kim ,  Yang-Pi Lin ,  Todd Charles Curtis ,  Charles Beaty Patterson

IPC: G21C3/07

CPC classification number: C23C4/08 ,  C23C4/06 ,  C23C4/073 ,  G21C3/324 ,  Y02E30/40

Abstract: A fuel rod includes a cladding tube with a wear-inhibiting coating. In one embodiment, the coating is made of a metallic powder material that is applied to the exterior surface of the cladding tube using a thermal spray process. In an alternative embodiment, the coating is a composite made of a metallic powder material, and a ceramic powder material or a metal oxide hard phase powder material that is simultaneously applied with the metallic powder material to coat the cladding tube. The coating can be applied to selected areas of the fuel rods where debris tends to fret the fuel rod.

Abstract translation: 燃料棒包括具有耐磨损涂层的包层管。 在一个实施例中，涂层由金属粉末材料制成，其使用热喷涂工艺施加到包层管的外表面。 在替代实施例中，涂层是由金属粉末材料和陶瓷粉末材料或金属氧化物硬质相粉末材料制成的复合材料，其同时施加金属粉末材料以涂覆包层管。 涂层可以应用于燃料棒的选定区域，其中碎片倾向于使燃料棒磨损。

公开(公告)号：US20060048870A1

公开(公告)日：2006-03-09

申请号：US10935157

申请日：2004-09-08

Applicant: David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

Inventor： David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

IPC: C22F1/18

CPC classification number: C22F1/186 ,  C22C16/00

Abstract: 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 .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.

Abstract translation: 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β-治疗。 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％的铁和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31.重量％，并且其特征在于具有平均值的第二相沉淀物 尺寸通常小于约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。

公开(公告)号：US09637809B2

公开(公告)日：2017-05-02

申请号：US12624845

申请日：2009-11-24

Applicant: Yang-Pi Lin ,  David W. White ,  Daniel R. Lutz

Inventor： Yang-Pi Lin ,  David W. White ,  Daniel R. Lutz

IPC: C22C16/00

CPC classification number: C22C16/00

Abstract: 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.

公开(公告)号：US09139895B2

公开(公告)日：2015-09-22

申请号：US10935157

申请日：2004-09-08

Applicant: David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

Inventor： David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

IPC: C22F1/18 ,  C22C16/00

CPC classification number: C22F1/186 ,  C22C16/00

Abstract: 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.

Abstract translation: 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。