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    Fuel assembly for nuclear reactor, method for producing the same and structural members for the same
    141.
    发明公开
    Fuel assembly for nuclear reactor, method for producing the same and structural members for the same 失效
    一种燃料组件，其用于核反应堆，处理为他们的这一部分的制备和结构。

    公开(公告)号：EP0353733A2

    公开(公告)日：1990-02-07

    申请号：EP89114266.3

    申请日：1989-08-02

    Applicant: HITACHI, LTD.

    Inventor： Kanno, Masayoshi ,  Inagaki, Masahisa ,  Takase, Iwao ,  Kuniya, Jiro ,  Maru, Akira ,  Yasuda, Tetsuro ,  Maki, Hideo

    IPC: G21C3/20

    CPC classification number: G21C3/34 ,  G21C3/07 ,  G21C3/20 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/202 ,  G21Y2004/30 ,  Y02E30/40

    Abstract: A fuel assembly for a nuclear reactor compris­ing a fuel cladding tube (11) of three-layer structure having an outer surface (16) in contact with reactor water of the nuclear reactor, an inner surface layer (14) in contact with the nuclear fuel, and an intermediate layer (15) interposed between the outer surface layer and the inner surface layer. the outer surface layer (16) is made of a Zr-based alloy containing Nb, Sn and Mo. The inner surface layer(14) is made of pure zirconium. The intermediate layer is made of a high ductility alloy which is higher in ductility than the outer surface layer (16) and is higher in strength than the inner surface layer(14).

    Abstract translation: 用于核反应堆，其包括三层结构的具有在与在与核燃料接触内表面层（14）的核反应堆的反应堆水接触外表面（16）的燃料包壳管（11）的燃料组件 和到外表面层和内表面层之间的中间层（15）。 外表面层（16）由Zr基合金含铌，Sn和Mo中的至少内表面层（14）是由纯锆的。 该中间层由高延展性合金所有其延展性比所述外表面层（16）和较高的强度比内表面层（14）更高的。

    Method of processing a control element to be immersed in coolant of a nuclear reactor
    145.
    发明公开
    Method of processing a control element to be immersed in coolant of a nuclear reactor 失效
    Verfahren zur Verarbeitung eines Steuerelementes zum Eintauchen inKernreaktorkühlmittel。

    公开(公告)号：EP0151920A1

    公开(公告)日：1985-08-21

    申请号：EP85100038.0

    申请日：1985-01-02

    Applicant: WESTINGHOUSE ELECTRIC CORPORATION

    Inventor： Weiss, Albert

    IPC: G21C3/06 ,  G21C7/10

    CPC classification number: G21C7/10 ,  G21C3/06 ,  G21Y2002/104 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/39 ,  Y10T29/49805 ,  Y10T29/49929

    Abstract: The invention relates to a method of rendering clad, pellet (13) containing elements (11), such as displacement rods to be used in nuclear reactors, essentially immune from undesirable deformation of the cladding and from a formation of undesirable gaps therewithin.
    As a last step in the making of such element, its cladding Is heated to a temperature sufficient to reduce the yield strength of the cladding and, while at said temperature, has isostatic pressure radially applied thereto to cause collapse of the cladding onto the pellets therein. Preferably, heating of the cladding is carried out in an atmosphere resulting in the formation of a beneficial oxide coating on the outer surface of the cladding.

    Abstract translation: 本发明涉及一种使含有元素（11）的包覆颗粒（13）的方法，例如在核反应堆中使用的置换棒，其基本上不受包层的不期望的变形以及在其中形成不期望的间隙。 ...作为制造这种元件的最后一步，其包层被加热到足以降低包层的屈服强度的温度，并且在所述温度下具有径向施加到其上的等静压力以引起 包覆在其中的颗粒上。 优选地，包层的加热在气氛中进行，导致在包层的外表面上形成有益的氧化物涂层。

    원자력발전소 내의 디지털 계측제어시스템을 위한 검사 장치 및 그 방법
    147.
    发明授权
    원자력발전소 내의 디지털 계측제어시스템을 위한 검사 장치 및 그 방법 有权
    用于测试核电厂数字仪表和控制系统的装置及其方法

    公开(公告)号：KR101594439B1

    公开(公告)日：2016-02-17

    申请号：KR1020140138506

    申请日：2014-10-14

    Applicant: 한국원자력연구원

    Inventor： 이승준 ,  정원대

    IPC: G21C17/00 ,  G01R31/3183 ,  G01R31/00

    CPC classification number: G01R31/3183 ,  G21C17/00 ,  G21Y2002/207 ,  G21Y2004/201

    Abstract: 본명세서는, 원자력발전소의디지털계측제어시스템의신뢰도를평가하기위해, 디지털계측제어시스템에결함을인가하고그 결함의영향을분석하는과정을자동으로수행하는원자력발전소내의디지털계측제어시스템을위한검사장치및 그방법에관한것으로서, 본발명의실시예에따른원자력발전소의디지털계측제어시스템을위한검사장치는, 디지털계측제어시스템의메모리에결함을인가하고, 그결함이반영된데이터를분석함으로써디지털계측제어시스템의신뢰도를평가할수 있다.

    Abstract translation: 本发明涉及一种用于核电站数字测量和控制系统的测试装置及其方法，其自动执行向数字测量和控制系统应用缺陷的过程，并分析缺陷的影响以估计可靠性 的核电站数字测控系统。 根据本发明的实施例，用于核电站数字测量和控制系统测试的装置将缺陷应用于数字测量和控制系统的存储器，并分析反映缺陷的数据，从而估计可靠性 的数字测控系统。 核电站数字测控系统的测试装置包括：一个缺陷应用模块; 组装过程模块; 执行模块; 和结果分析模块。

    원자로
    148.
    发明公开
    원자로 无效
    核反应堆

    公开(公告)号：KR1020120125012A

    公开(公告)日：2012-11-14

    申请号：KR1020110043032

    申请日：2011-05-06

    Applicant: 울산과학기술원

    Inventor： 방인철 ,  김지현 ,  박성대 ,  이승원 ,  강사라 ,  김성만

    IPC: G21C11/08 ,  G21C9/00

    CPC classification number: Y02E30/40 ,  G21C13/02 ,  G21C11/08 ,  G21Y2002/30 ,  G21Y2004/201

    Abstract: PURPOSE: A nuclear reactor is provided to improve cooling capability of a nuclear reactor external wall by preventing a film formed on a nuclear reactor external wall. CONSTITUTION: A container(100) is formed into a coupling structure of a hemispheric shape. The container accommodates core melt(110) in a lower part. A thermal shielding body(200) covers an external wall of the container. A nuclear reactor cavity(300) includes thermal shielding and the container. A partition wall(230) is formed from the thermal shielding body to the exterior wall of the container. The partition wall is formed with the exterior wall of the container. A guide wing(120) is formed between the partition walls.

    Abstract translation: 目的：提供核反应堆，以通过防止在核反应堆外墙上形成的膜来改善核反应堆外壁的冷却能力。 构成：容器（100）形成为半球形状的联接结构。 容器容纳下部的芯熔体（110）。 热屏蔽体（200）覆盖容器的外壁。 核反应堆空腔（300）包括热屏蔽和容器。 分隔壁（230）由热屏蔽体形成到容器的外壁。 分隔壁与容器的外壁形成。 在分隔壁之间形成引导翼（120）。

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