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。

公开(公告)号：US20170260613A1

公开(公告)日：2017-09-14

申请号：US15610533

申请日：2017-05-31

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 ,  C22C27/06 ,  C22C1/02

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. 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.

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。

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。

公开(公告)号：US20200283885A1

公开(公告)日：2020-09-10

申请号：US16762247

申请日：2018-11-14

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Jung Hwan PARK ,  Hyun Gil KIM ,  Yang II JUNG ,  Dong Jun PARK ,  Byoung Kwon CHOI ,  Young Ho LEE ,  Jae Ho YANG

IPC: C23C14/16 ,  B32B15/01 ,  C23C14/32 ,  G21C3/07

Abstract: The present invention relates to a zirconium alloy cladding with improved oxidation resistance at a high temperature and a method of manufacturing the same. More particularly, the zirconium alloy cladding includes a zirconium alloy cladding; and a Cr—Al thin film coated on the cladding, wherein the thin film is deposited through arc ion plating and the content of Al in the thin film is 5% by weight to 20% by weight.