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    Coating a nuclear fuel with a burnable poison
    24.
    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

    Applicant: Kenneth C. Radford

    Inventor： Kenneth C. Radford

    IPC: G21C3/20 ,  G21C3/18 ,  G21C3/62 ,  G21C7/04 ,  G21C3/00

    CPC classification number: G21C7/04 ,  G21C3/18 ,  G21Y2002/104 ,  G21Y2002/201 ,  G21Y2002/206 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/39

    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
    27.
    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

    Applicant: Daniel Lutz ,  Gerald Potts ,  Yang-Pi Lin ,  Sheikh Mahmood ,  Mark Dubecky ,  David White ,  John Schardt

    Inventor： Daniel Lutz ,  Gerald Potts ,  Yang-Pi Lin ,  Sheikh Mahmood ,  Mark Dubecky ,  David White ,  John Schardt

    IPC: G21C1/04

    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。

    Fuel channel box and a method of manufacturing the same
    28.
    发明授权
    Fuel channel box and a method of manufacturing the same 有权
    燃油通道箱及其制造方法

    公开(公告)号：US06704386B2

    公开(公告)日：2004-03-09

    申请号：US10285421

    申请日：2002-11-01

    Applicant: Michio Nakayama ,  Takehiro Seto ,  Tatsuo Seki ,  Isao Kurihara

    Inventor： Michio Nakayama ,  Takehiro Seto ,  Tatsuo Seki ,  Isao Kurihara

    IPC: G21C307

    CPC classification number: G21C3/324 ,  G21C21/00 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: A fuel channel box manufacturing method processes a fuel channel box of a zirconium-base alloy by a beta-quench treatment that heats the fuel channel box by a heating coil. The distance between the heating coil and the opposite walls of the fuel channel box is controlled so that temperature differences between the opposite walls of the fuel channel box are reduced. The fuel channel box of a zirconium-base alloy is heated at a temperature in a temperature range including &bgr;-phase temperatures so that temperature difference between the opposite walls is 50° C. or below. The fuel channel box manufacturing method is capable of manufacturing a fuel channel box that is not subject to significant irradiated bow even if a deflection is produced therein originally when the same is manufactured and of manufacturing the fuel channel box at a high production efficiency.

    Abstract translation: 燃料通道箱制造方法通过加热线圈对燃料通道箱加热的β-淬火处理来处理锆基合金的燃料通道箱。 控制加热线圈与燃料通道箱的相对壁之间的距离，使得燃料通道箱的相对壁之间的温度差减小。 锆基合金的燃料通道箱在包括β相温度的温度范围内被加热，使得相对壁之间的温度差为50℃或更低。 燃料通道箱的制造方法能够制造即使在其制造时原来产生偏转并且以高生产效率制造燃料通道箱时，也不会受到显着的照射弓的燃料通道箱的影响。

    Neutronic fuel element fabrication
    29.
    发明授权
    Neutronic fuel element fabrication 失效

    公开(公告)号：US06697448B1

    公开(公告)日：2004-02-24

    申请号：US04594943

    申请日：1966-11-16

    Applicant: George Korton

    Inventor： George Korton

    IPC: G21C304

    CPC classification number: G21C3/04 ,  G21C3/07 ,  G21C3/60 ,  G21C21/02 ,  G21Y2002/302 ,  G21Y2004/201 ,  G21Y2004/301 ,  Y02E30/35 ,  Y02E30/38 ,  Y10T29/49373

    Abstract: This disclosure describes a method for metallurgically bonding a complete leak-tight enclosure to a matrix-type fuel element penetrated longitudinally by a multiplicity of coolant channels. Coolant tubes containing solid filler pins are disposed in the coolant channels. A leak-tight metal enclosure is then formed about the entire assembly of fuel matrix, coolant tubes and pins. The completely enclosed and sealed assembly is exposed to a high temperature and pressure gas environment to effect a metallurgical bond between all contacting surfaces therein. The ends of the assembly are then machined away to expose the pin ends which are chemically leached from the coolant tubes to leave the coolant tubes with internal coolant passageways. The invention described herein was made in the course of, or under, a contract with the U.S. Atomic Energy Commission. It relates generally to fuel elements for neutronic reactors and more particularly to a method for providing a leak-tight metal enclosure for a high-performance matrix-type fuel element penetrated longitudinally by a multiplicity of coolant tubes. The planned utilization of nuclear energy in high-performance, compact-propulsion and mobile power-generation systems has necessitated the development of fuel elements capable of operating at high power densities. High power densities in turn require fuel elements having high thermal conductivities and good fuel retention capabilities at high temperatures. A metal clad fuel element containing a ceramic phase of fuel intimately mixed with and bonded to a continuous refractory metal matrix has been found to satisfy the above requirements. Metal coolant tubes penetrate the matrix to afford internal cooling to the fuel element while providing positive fuel retention and containment of fission products generated within the fuel matrix. Metal header plates are bonded to the coolant tubes at each end of the fuel element and a metal cladding or can completes the fuel-matrix enclosure by encompassing the sides of the fuel element between the header plates.

    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method
    30.
    发明申请
    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method 失效
    表面处理反应器构件的方法和使用表面处理方法制造反应器构件的方法

    公开(公告)号：US20030129929A1

    公开(公告)日：2003-07-10

    申请号：US10190517

    申请日：2002-07-09

    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.

    Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    IPC: B24B001/00

    CPC classification number: G21C3/07 ,  G21C3/12 ,  G21Y2002/103 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40 ,  Y10S148/908 ,  Y10S376/90

    Abstract: A method of surface-treating a reactor member for effectively removing a Cr-deficient layer and a work-hardened layer considered to be a cause of stress-corrosion cracking (SCC) under low-stress conditions. The method of surface-treating a reactor member which is worked by bending (step 1) and then processed by a heat treatment (step 2), in which a work-hardened layer is formed by the bending, and in which a Cr-deficient layer is formed due to an oxide film attached by the heat treatment, uses at least one of: acid wash; grinding; electrolytic polishing; electro-discharge machining; surface cutting; surface deoxidation and softening; wet blasting; laser machining; or surface plating (step 3) to remove the work-hardened layer and the Cr-deficient layer from the reactor member or to prevent contact of the work-hardened layer and the Cr-deficient layer of the reactor member with a primary coolant.

    Abstract translation: 在低应力条件下，有效去除Cr缺陷层和被认为是应力腐蚀开裂原因（SCC）的加固硬化层的反应器构件的表面处理方法。 表面处理通过弯曲（步骤1）进行加工，然后通过热处理（步骤2）进行加工的反应器构件的表面处理方法，其中通过弯曲形成加工硬化层，并且其中Cr缺陷 由于通过热处理而附着的氧化膜形成层，使用以下中的至少一种：酸洗; 研磨 电解抛光; 放电加工; 表面切割; 表面脱氧和软化; 湿喷 激光加工; 或表面电镀（步骤3）以从反应器构件去除加固硬化层和Cr缺陷层，或者防止加固硬化层和反应器构件的Cr缺陷层与初级冷却剂接触。

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