中科微点-全球专利检索

  1. Login
  2. Sign Up

Search Results

7 records (took 0.012 seconds)

    Chromium-Aluminum Binary Alloy Having Excellent Corrosion Resistance and Method of Manufacturing Thereof
    1.
    发明申请
    Chromium-Aluminum Binary Alloy Having Excellent Corrosion Resistance and Method of Manufacturing Thereof 审中-公开
    具有优异耐腐蚀性的铬铝二元合金及其制造方法

    公开(公告)号：US20160108507A1

    公开(公告)日：2016-04-21

    申请号：US14695792

    申请日：2015-04-24

    Applicant: Korea Atomic Energy Research Institute

    Inventor： Hyun Gil KIM ,  Il Hyun KIM ,  Yang-Il JUNG ,  Dong Jun PARK ,  Jung Hwan PARK ,  Jeong-Yong PARK ,  Yang-Hyun KOO

    IPC: C22F1/11 ,  C22C1/02 ,  C22C27/06

    CPC classification number: C22F1/11 ,  C22C1/02 ,  C22C16/00 ,  C22C19/03 ,  C22C27/06 ,  C23C4/08

    Abstract: The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance, including: 1 to 40% by weight of aluminum (Al), the balance of chromium (Cr), and other unavoidable impurities with respect to a total weight of the alloy, and a method of producing a chromium-aluminum binary alloy with excellent corrosion resistance, the method including: (Step 1) mixing and melting a raw material comprising: 1 to 40% by weight of aluminum (Al), the balance of chromium (Cr), and other unavoidable impurities with respect to a total weight of the alloy; and (Step 2) solution treating the alloy melted in Step 1. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.

    Abstract translation: 本公开内容涉及耐腐蚀性优异的铬 - 铝二元合金及其制造方法，更具体地说，涉及具有优异耐腐蚀性的铬 - 铝二元合金，包括：1〜40重量％的铝（Al ），相对于合金的总重量的铬（Cr）和其他不可避免的杂质的平衡，以及具有优异的耐腐蚀性的铬 - 铝二元合金的制造方法，其包括：（步骤1） 熔融原料，其包含：相对于合金的总重量为1〜40重量％的铝（Al），余量的铬（Cr）和其他不可避免的杂质; 和（步骤2）处理在步骤1中熔化的合金的溶液。铬铝二元合金可以容易地制造并具有延展性，因此作为需要耐高温耐腐蚀性和耐磨性的材料的涂层材料被高度适用。

    CLADDING TUBES COATING APPARATUS
    4.
    发明公开
    CLADDING TUBES COATING APPARATUS 审中-公开

    公开(公告)号：US20240254615A1

    公开(公告)日：2024-08-01

    申请号：US18408870

    申请日：2024-01-10

    Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

    Inventor： Hyun Gil KIM ,  Sung Eun KIM ,  Jongdae HONG ,  HongRyoul OH

    IPC: C23C14/14 ,  C23C14/32 ,  C23C14/50 ,  C23C14/54

    CPC classification number: C23C14/14 ,  C23C14/325 ,  C23C14/505 ,  C23C14/542

    Abstract: A cladding tube coating apparatus includes a chamber unit configured to create a zirconium alloy coating environment using arc ion plating, a rotating support portion provided in the chamber unit to accommodate a plurality of cladding tubes, which are coating objects, and a target portion provided in the chamber unit toward the plurality of cladding tubes accommodated in the rotation support portion and ionized as an oxidation-resistant material is melted and evaporated due to an arcing phenomenon, wherein the rotation support portion includes a plurality of rotary tables on which the plurality of cladding tubes are rotationally supported, supports the rotary tables so that a rotation speed of the plurality of cladding tubes is constant at a preset speed, and supports the rotary table to maintain a coating thickness uniformly in longitudinal and circumferential directions.

    ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A SEVERE REACTOR OPERATION CONDITION AND METHODS OF PREPARING A ZIRCONIUM ALLOY NUCLEAR CLADDING BY USING THEREOF
    6.
    发明申请
    ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A SEVERE REACTOR OPERATION CONDITION AND METHODS OF PREPARING A ZIRCONIUM ALLOY NUCLEAR CLADDING BY USING THEREOF 有权
    用于在严重反应器操作条件下具有超级氧化电阻的核燃料层压的ZIRCONIUM合金及其使用的制备ZIRCONIUM合金核层的方法

    公开(公告)号：US20130220495A1

    公开(公告)日：2013-08-29

    申请号：US13747763

    申请日：2013-01-23

    Applicant: Korea Atomic Energy Research Institute ,  Korea Hydro and Nuclear Power Co., Ltd.

    Inventor： Jeong-Yong PARK ,  Yang-II JUNG ,  Hyun Gil KIM ,  Byoung-Kwon CHOI ,  Sang Yoon PARK ,  Dong Jun PARK ,  Yang-Hyun KOO

    IPC: G21C3/07

    CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C21/10 ,  Y02E30/40

    Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety.

    Abstract translation: 公开了一种在严格的反应器运行条件下具有良好的抗氧化性的核燃料包覆用锆合金，以及通过使用它们制备锆合金核燃料包层的方法。 锆合金含有1.8〜2.0重量％的铌（Nb）; 选自铁（Fe），铬（Cr）和铜（Cu）中的至少一种元素; 0.1〜0.15重量％的氧（O）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 Fe的量为0.1〜0.4重量％，Cr的含量为0.05〜0.2重量％，Cu的含量为0.03〜0.2重量％。 在反应堆的事故状态以及反应堆的正常运行状态下，在严格的反应堆操作条件下，可以确认核燃料包层的良好的抗氧化性，从而提高经济效率和安全性。

    ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A REACTOR ACCIDENT CONDITION, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS PREPARED BY USING THEREOF AND METHODS OF PREPARING THE SAME
    7.
    发明申请
    ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A REACTOR ACCIDENT CONDITION, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS PREPARED BY USING THEREOF AND METHODS OF PREPARING THE SAME 有权
    用于在反应器事故状态下具有超级氧化电阻的核燃料层压的ZIRCONIUM合金，使用其制备的ZIRCONIUM合金核燃料层和其制备方法

    公开(公告)号：US20130220493A1

    公开(公告)日：2013-08-29

    申请号：US13747042

    申请日：2013-01-22

    Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE ,  KOREA HYDRO AND NUCLEAR POWER CO., LTD.

    Inventor： Jeong-Yong PARK ,  Hyun Gil KIM ,  Byoung-Kwon CHOI ,  Sang Yoon PARK ,  Yang-II JUNG ,  Dong Jun PARK ,  Yang-Hyun KOO

    IPC: G21C3/07

    CPC classification number: G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C21/10 ,  Y02E30/40

    Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (0); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.

    Abstract translation: 公开了一种用于核燃料包层的锆合金，其在反应堆事故条件下具有良好的抗氧化性，通过使用它制备的锆合金核燃料包覆层及其制备方法。 锆合金含有1.0〜1.2重量％的铌（Nb）; 选自锡（Sn），铁（Fe）和铬（Cr）中的至少一种元素; 0.02〜0.1重量％的铜（Cu）; 0.1〜0.15重量％的氧（0）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 Sn的量为0.1〜0.3重量％，Fe的量为0.3〜0.8重量％，Cr的含量为0.1〜0.3重量％。 可以在事故条件以及反应堆的正常运行条件下确认核燃料包层的良好的抗氧化性，从而提高经济效率和安全性。

Patent Agency Ranking