Fuel channel box and a method of manufacturing the same
    51.
    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

    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
    52.
    发明授权

    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

    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
    53.
    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

    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。

    Fuel rod cladding tube for a boiling water reactor fuel rod and the production thereof
    54.
    发明授权
    Fuel rod cladding tube for a boiling water reactor fuel rod and the production thereof 失效
    用于沸水反应堆燃料棒的燃料棒包覆管及其生产

    公开(公告)号:US06503346B1

    公开(公告)日:2003-01-07

    申请号:US09381185

    申请日:1999-09-13

    Inventor: Eckard Steinberg

    Abstract: Cladding tube for a fuel rod for a boiling water reactor fuel element, and its production. The cladding tube is composed practically homogeneously of the constituents of zircaloy and, with the ductility parameter &ggr;=3{square root over ((kd))}/(fr)2≦3.5 (&ggr;=ductility parameter, KD=mean grain diameter; fr=Kearns factor), has an elongation at break of at least 20%, set by low-temperature treatment of an extruded tube blank. The starting body used for the extrusion has a defined distribution of precipitated secondary particles which is produced by &bgr;-quenching and differs in the areas which form the inner surface and outer surface of the extruded tube. At the inner surface, the particles have a greater diameter and are at a greater average distance apart, this distribution being described by the “spacing”.

    Abstract translation: 用于沸水反应堆燃料元件燃料棒的包层管及其生产。 包层管实际上是均匀地由锆石的成分组成,延性参数γ= 3 {平方根超过((kd)/(fr)2 <= 3.5(γ=延展性参数,KD =平均粒径; fr = Kearns因子),具有至少20%的断裂伸长率,通过挤压管坯的低温处理来设定。用于挤出的起始体具有由β-淬火产生的沉淀二次粒子的确定分布 并且在形成挤出管的内表面和外表面的区域中不同,在内表面处,颗粒具有更大的直径并且具有更大的平均距离,该分布由“间距”描述。

    Laser maintaining and repairing apparatus
    55.
    发明授权
    Laser maintaining and repairing apparatus 失效
    激光维修和修理设备

    公开(公告)号:US6163012A

    公开(公告)日:2000-12-19

    申请号:US937663

    申请日:1997-09-24

    Abstract: A laser maintaining and repairing apparatus including a laser oscillator 7, beam guiding apparatus 8 connected to guide a laser beam of the laser oscillator 7, and emitting head 12 for converging the laser beam from the beam guiding apparatus 8 and emitting the beam to a portion to be processed. The beam guiding apparatus 8 includes liquid-tight tubular beam guiding members 9a to 9h. The beam guiding members 9a to 9h are provided with reflecting members 13a, 13b and at least one of mechanisms 10a, 10b and 11a, 11b for providing horizontal turning, horizontal extending, vertical turning and vertical extending operations at the beam guiding members 9a to 9h. With the laser maintaining and repairing apparatus of the noted structure, a laser beam of high energy density can be utilized and processing by the laser beam can be facilitated or the applying range can be increased.

    Abstract translation: 包括激光振荡器7,引导激光振荡器7的激光束的光束引导装置8和用于会聚来自光束引导装置8的激光束并将光束发射到一部分的激光器维持和修复装置 待处理。 光束引导装置8包括液密的管状光束引导部件9a至9h。 光束引导部件9a至9h设置有反射部件13a,13b以及用于在光束引导部件9a至9h处提供水平转动,水平延伸,垂直转动和垂直延伸操作的机构10a,10b和11a,11b中的至少一个 。 利用所述结构的激光维持和修复装置,可以利用高能量密度的激光束并且可以促进激光束的处理或者可以增加施加范围。

    Zirconium alloy tube for a nuclear reactor fuel assembly, and method for
making same
    56.
    发明授权
    Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same 失效
    用于核反应堆燃料组件的锆合金管及其制造方法

    公开(公告)号:US5887045A

    公开(公告)日:1999-03-23

    申请号:US875481

    申请日:1997-07-29

    Abstract: A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.

    Abstract translation: PCT No.PCT / FR96 / 00137 Sec。 371日期1997年7月29日第 102(e)日期1997年7月29日PCT 1996年1月26日PCT PCT。 公开号WO96 / 24140 日期1996年8月8日一种用于构成用于核燃料组件的包层或导管的全部或一部分的锆基合金管。 该管由合金含有1.0-1.7%的锡,0.55-0.80%的铁,0.20-0.60%的铬和/或钒和0.10-0.18%的氧,其中50-200 碳的碳和50-120ppm的硅。 该合金还含有锆和不可避免的杂质,并且完全重结晶。

    Irradiated intermetallic compound containing part of light-water reactor
    57.
    发明授权
    Irradiated intermetallic compound containing part of light-water reactor 失效
    含有部分轻水反应器的辐照金属间化合物

    公开(公告)号:US5735974A

    公开(公告)日:1998-04-07

    申请号:US763112

    申请日:1996-12-10

    Abstract: A part of a light-water reactor, for example, a cladding for a light-water reactor has at least a portion made of an intermetallic compound, such as Ni.sub.3 Al, Ni.sub.2 Al.sub.3, TiAl, Ti.sub.3 Al, Pt.sub.2 Si, PtSi, FeAl.sub.2, CoAl, and MoSi.sub.2, thereby having limited irradiation degradation by fast neutrons, improved ductility and usability at high temperatures the intermetallic compound is produced by a process comprising a step of irradiating the intermetallic compound with at least one selected from the group consisting of a neutron, a light ion, and an electron. The intermetallic compound may contain a twin and a third additional element segregatedly present or forms a second phase at or near to a grain boundary.

    Abstract translation: 轻水反应器的一部分,例如用于轻水反应器的包层至少具有由金属间化合物如Ni3Al,Ni2Al3,TiAl,Ti3Al,Pt2Si,PtSi,FeAl2,CoAl和 MoSi2,因此通过快速中子的辐射降解受限,延展性和高温下的可用性,金属间化合物通过包括以下步骤的方法产生:金属间化合物与选自以下的至少一种:中子,轻离子 ,和电子。 金属间化合物可以含有在晶界处或附近分离存在或形成第二相的双和第三附加元素。

    Fuel element for pressurized--water reactor with guide tubes finally
heat-treated in two steps
    58.
    发明授权
    Fuel element for pressurized--water reactor with guide tubes finally heat-treated in two steps 失效
    用于带有导管的加压水反应器的燃料元件最终在两个步骤中热处理

    公开(公告)号:US5654993A

    公开(公告)日:1997-08-05

    申请号:US564191

    申请日:1995-12-18

    Abstract: The invention relates to a fuel element for a pressurized-water reactor comprising a number of fuel rods arranged in a square lattice and wherein certain positions in the lattice contain guide tubes for receiving control rods, wherein the fuel element can be used for higher burnup by manufacturing the guide tubes of the element such that their irradiation-induced growth is reduced and their corrosion resistance is increased compared with conventionally manufactured guide tubes. This is achieved by finally heat-treating the guide tubes in two steps, the first step being a beta quenching and the second step a heat treatment in the alpha-phase region.

    Abstract translation: PCT No.PCT / SE94 / 00644 Sec。 371 1995年12月18日第 102(e)1995年12月18日的PCT PCT 1994年6月29日PCT公布。 公开号WO95 / 01639 日期1995年1月12日本发明涉及一种用于加压水反应器的燃料元件,其包括以正方形格子布置的多个燃料棒,并且其中格子中的某些位置包含用于接收控制棒的引导管,其中该燃料元件可以 用于通过制造元件的引导管以使其照射诱导的生长减少并且与常规制造的引导管相比它们的耐腐蚀性增加而用于更高的燃耗。 这通过以两个步骤最后热处理导管来实现,第一步是β淬灭,第二步是在α相区域中进行热处理。

    Method of maintaining housing of reactor pressure vessel and heat
treatment equipment therefor
    60.
    发明授权
    Method of maintaining housing of reactor pressure vessel and heat treatment equipment therefor 失效
    维护反应堆压力容器及其热处理设备的方法

    公开(公告)号:US5329099A

    公开(公告)日:1994-07-12

    申请号:US704289

    申请日:1991-05-22

    Abstract: A method of maintaining the housing of a reactor pressure vessel having: a reactor pressure vessel into which cooling water is introduced; a cylindrical housing which penetrates an end bracket of the reactor pressure vessel; and a circumferential weld for securing the intermediate portion of the housing to the reactor pressure vessel by welding, the method of maintaining a housing of a reactor pressure vessel comprising the steps of: remaining the cooling water in the reactor pressure vessel; preventing leakage of the cooling water in the reactor pressure vessel through the housing by sealing the housing; making the inside portion of the housing lower than the seal to be a hollow space of a gas atmosphere; heating a heat affected zone due to welding by using a heating device inserted into the hollow space from a lower portion so as to compressive-yield the inner surface of the housing in the heat affected portion upper than the circumferential weld and tensile-yield the outer surface; and cooling heated portion inside of the housing, which has been yielded, so as to tensile-yield the inner surface of the housing by using a cooling device inserted into the housing from a lower portion, whereby compressive stress is allowed to remain in the tensile-yielded portion.

    Abstract translation: 一种维持反应堆压力容器的壳体的方法,该反应堆压力容器具有:引入冷却水的反应堆压力容器; 圆柱形壳体,其穿过反应堆压力容器的端部支架; 以及用于通过焊接将壳体的中间部分固定到反应堆压力容器的圆周焊缝,保持反应堆压力容器的壳体的方法,包括以下步骤:在反应堆压力容器中保留冷却水; 防止反应堆压力容器内的冷却水通过密封壳体而通过壳体泄漏; 使壳体的内部低于密封件成为气体气氛的中空空间; 通过使用从下部插入到中空空间中的加热装置来加热受热影响区域,以便在高于周向焊缝的热影响部分中压缩屈服于壳体的内表面并拉伸屈服外侧 表面; 以及已经产生的壳体内部的冷却加热部分,以便通过使用从下部插入到壳体中的冷却装置来拉伸屈服壳体的内表面,由此使压缩应力保持在拉伸 硬部分。

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