中科微点-全球专利检索

  1. Login
  2. Sign Up

Search Results

255 records (took 0.022 seconds)

    Cladding tube for nuclear fuel and nuclear fuel element having this cladding tube
    91.
    发明授权
    Cladding tube for nuclear fuel and nuclear fuel element having this cladding tube 失效
    用于核燃料的包层管和具有该包层管的核燃料元件

    公开(公告)号：US4863679A

    公开(公告)日：1989-09-05

    申请号：US59175

    申请日：1987-06-12

    Applicant: Hiromichi Imahashi ,  Toshio Kubo ,  Kazumi Asahi ,  Hideyuki Mukai ,  Keizo Ogata

    Inventor： Hiromichi Imahashi ,  Toshio Kubo ,  Kazumi Asahi ,  Hideyuki Mukai ,  Keizo Ogata

    IPC: G21C3/20

    CPC classification number: G21C3/20 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/30 ,  Y02E30/40

    Abstract: Disclosed are a cladding tube for a nuclear fuel and a nuclear fuel element incorporating the cladding tube. The cladding tube consists of an inner zirconium liner layer and an outer zirconium alloy layer. The cladding tube has at least one of the following features: (I) the ratio a/b of the oxygen content a to iron content b in the zirconium liner layer is greater than 1.0, (II) the zirconium liner layer is made of a zirconium into the matrix of which impurities are dissolved, and (III) the second phase particles having microscopic sizes and dispersed in the inner surface of the zirconium liner layer and/or the outer surface of the zirconium alloy layer have been removed substantially. Owing to these features, undesirable stress corrosion cracking and local corrosion are remarkably suppressed in the cladding tube and the nuclear fuel element of the invention.

    Abstract translation: 公开了一种用于核燃料的包覆管和结合有包层管的核燃料元件。 包层管由内锆衬层和外锆合金层组成。 包壳管具有以下特征中的至少一个：（I）锆衬层中氧含量a与铁含量b的比a / b大于1.0，（II）锆衬层由 锆溶解在其中溶解有杂质的基质中，并且（III）已经除去了具有微观尺寸并分散在锆衬层的内表面和/或锆合金层的外表面的第二相颗粒。 由于这些特征，在本发明的包层管和核燃料元件中，显着地抑制了不期望的应力腐蚀开裂和局部腐蚀。

    Heat treated tube
    94.
    发明授权
    Heat treated tube 失效
    热处理管

    公开(公告)号：US4576654A

    公开(公告)日：1986-03-18

    申请号：US438515

    申请日：1982-11-01

    Applicant: Fletcher C. Eddens ,  David W. White ,  John L. Harmon

    Inventor： Fletcher C. Eddens ,  David W. White ,  John L. Harmon

    IPC: C22F1/18 ,  G21C21/02

    CPC classification number: C22F1/186 ,  G21C21/02 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201

    Abstract: There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumference and a less corrosion-resistant metallurgical condition at the inner circumference. The metallurgical gradient can be generated by heating an outer circumferential portion of the tube to the high alpha or mixed alpha plus beta range while maintaining the inner surface at a lower temperature, followed by cooling of the tube.

    Abstract translation: 提供了具有耐腐蚀性提高的锆合金包覆管的核燃料元件。 包层管包括横跨管壁的宽度的冶金梯度，其中管在外周具有更耐蚀的冶金条件，在内圆周处具有较少的耐腐蚀冶金条件。 可以通过将管的外周部分加热到高α或混合α+β范围同时将内表面保持在较低温度，随后冷却管而产生冶金梯度。

    Method of manufacturing reactor member by using the surface treatment method
    98.
    发明授权
    Method of manufacturing reactor member by using the surface treatment method 失效
    使用表面处理方法制造反应器部件的方法

    公开(公告)号：US07459037B2

    公开(公告)日：2008-12-02

    申请号：US11041305

    申请日：2005-01-25

    Applicant: Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    IPC: C21D9/02 ,  C21D7/06 ,  C21D7/08

    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，有效地除去被认为是应力腐蚀开裂原因（SCC）的Cr缺陷层和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。

    Method of surface-treating reactor member and method of manufacturing reactor member by using the surface treatment method
    99.
    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：US20050220260A1

    公开(公告)日：2005-10-06

    申请号：US11041305

    申请日：2005-01-25

    Applicant: Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

    IPC: G21C21/00 ,  G21C3/07 ,  G21C3/12 ,  G21C3/33 ,  G21C15/00

    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，有效地除去被认为是应力腐蚀开裂原因（SCC）的Cr缺陷层和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。

Patent Agency Ranking