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    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method
    3.
    发明授权
    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：US06869338B2

    公开(公告)日：2005-03-22

    申请号：US10190517

    申请日：2002-07-09

    Applicant: Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    IPC: G21C21/00 ,  G21C3/07 ,  G21C3/12 ,  G21C3/33 ,  B24B1/00

    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。

    Zirconium-base alloy and nuclear reactor component comprising the same
    4.
    发明授权
    Zirconium-base alloy and nuclear reactor component comprising the same 失效
    锆基合金和包含其的核反应堆组分

    公开(公告)号：US06690759B1

    公开(公告)日：2004-02-10

    申请号：US10263714

    申请日：2002-10-04

    Applicant: Shuichi Nanikawa ,  Shinji Ishimoto ,  Toshio Kubo

    Inventor： Shuichi Nanikawa ,  Shinji Ishimoto ,  Toshio Kubo

    IPC: G21C307

    CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C1/084 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: Disclosed herein are zirconium-base alloys excellent in both corrosion resistance and hydrogen absorption property, useful as materials for nuclear reactors. Such a zirconium-base alloy for nuclear reactors comprises 0.5-2 wt. % Sn, 0.07-0.6 wt. % Fe, 0.03-0.2 wt. % Ni, 0.05-0.2 wt. % Cr, and the balance being zirconium and unavoidable impurities, wherein the Fe content (X wt. %) of the zirconium-base alloy and the mean size (Y nm) of precipitates in the zirconium-base alloy are present in a region on the x (Fe content X) and y (mean precipitate size) rectangular coordinates, surrounded by the following five lines: i) Y=−444×X+154, ii) Y=910×X−46, iii) Y=0, iv) Y=300, and v) X=0.6.

    Abstract translation: 本文公开了耐腐蚀性和吸氢性优异的锆基合金，可用作核反应堆的材料。 这种用于核反应堆的锆基合金包含0.5-2wt。 ％Sn，0.07-0.6重量％ ％Fe，0.03-0.2重量％ ％Ni，0.05-0.2重量％ ％Cr，余量为锆和不可避免的杂质，其中锆基合金的Fe含量（X重量％）和锆基合金中析出物的平均粒径（Ynm）存在于 由以下五行包围的x（Fe含量X）和y（平均沉淀物大小）直角坐标：i）Y = -444xX + 154，ii）Y = 910xX-46，iii）Y = 0，iv）Y = 300，v）X = 0.6。

    Nuclear reaction fuel assembly for a nuclear reactor fuel assembly
    5.
    发明授权
    Nuclear reaction fuel assembly for a nuclear reactor fuel assembly 有权
    核反应堆燃料组件的核反应燃料组件

    公开(公告)号：US6154514A

    公开(公告)日：2000-11-28

    申请号：US132475

    申请日：1998-08-11

    Applicant: Kazuo Murakami ,  Shinichi Shiraishi ,  Kiyoshi Izumi

    Inventor： Kazuo Murakami ,  Shinichi Shiraishi ,  Kiyoshi Izumi

    IPC: G21C3/33 ,  G21C3/12 ,  G21C19/06

    CPC classification number: G21C3/12 ,  G21Y2002/104 ,  G21Y2004/201 ,  G21Y2004/305 ,  Y02E30/40

    Abstract: An upper hold-down spring structure for a nuclear reactor fuel assembly. A hold down spring 20 mounted on an upper surface of an upper nozzle 11 of a fuel assembly for a pressurized water reactor is composed of an upper plate spring 21 having plastic spring characteristics and a lower plate spring 23, base ends of which are fixed with a fastening bolt 18 at a common position. The upper spring 21 and the lower spring 23 are made of precipitation hardened nickel base alloy and the thickness of the springs are determined so as to keep the stresses generated less sensitive to stress corrosion cracking.

    Abstract translation: 用于核反应堆燃料组件的上压紧弹簧结构。 安装在用于压水反应堆的燃料组件的上喷嘴11的上表面上的按压弹簧20由具有塑料弹簧特性的上板簧21和下板弹簧23组成，底板弹簧21的基端固定有 在同一位置的紧固螺栓18。 上弹簧21和下弹簧23由沉淀硬化的镍基合金制成，并且弹簧的厚度被确定为保持对应力腐蚀开裂不敏感的应力。

    Manufacture of zirconium cladding tube with internal liner
    8.
    发明授权
    Manufacture of zirconium cladding tube with internal liner 失效
    具有内衬的锆包层管的制造

    公开(公告)号：US5620536A

    公开(公告)日：1997-04-15

    申请号：US284648

    申请日：1994-08-11

    Applicant: Mats Dahlb ack

    Inventor： Mats Dahlb ack

    IPC: G21C3/07 ,  C21D9/08 ,  C22F1/00 ,  C22F1/18 ,  G21C3/06 ,  G21C3/20 ,  G21C21/02

    CPC classification number: G21C21/02 ,  C22F1/186 ,  G21C3/20 ,  G21Y2002/103 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: A method of manufacturing nuclear fuel elements which include fuel rods whose cladding tubes are provided with an internal liner layer to obtain PCT resistance in the nuclear fuel element involves carefully choosing parameters for heat treatment of the inner component even from the machining of an ingot of the inner component. The internal layer of zirconium or a zirconium alloy, suitable as inner layer in a PCI-resistant cladding, from the fabrication of an ingot of the inner component up to the completion of a cladding tube, including forging, rolling, extrusion, heat treatment and final heat treatment, is manufactured in such a way that the temperature in the inner component never exceeds the temperature when an incipient phase transformation to beta phase takes place.

    Abstract translation: PCT No.PCT / SE93 / 01070 Sec。 371日期：1994年8月11日 102（e）日期1994年8月11日PCT提交1993年12月15日PCT公布。 公开号WO94 / 15343 日期1994年7月7日制造核燃料元件的制造方法，其包括燃料棒，其包层管设有内衬层，以获得核燃料元件中的PCT耐性，包括即使从加工中仔细选择内部部件的热处理参数 的内部组件的锭。 从内部组件的锭的制造到包覆管的完成（包括锻造，轧制，挤出，热处理）和包覆管的完成的锆或锆合金的内层，适合作为耐PCI包层中的内层 最终热处理以这样的方式制造，使得内部组分中的温度不会超过当β相的初期相变发生时的温度。

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