公开(公告)号：US20220161325A1

公开(公告)日：2022-05-26

申请号：US17528329

申请日：2021-11-17

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Hyun Gil KIM ,  Yang II Jung ,  Dong Jun Park ,  Jung Hwan Park ,  Jong Dae Hong ,  II Hyun Kim

IPC: B22F10/25 ,  H01M8/021 ,  H01M8/0228 ,  B33Y10/00 ,  B33Y80/00

Abstract: Disclosed are a method for coating metal, a metal member comprising the coating layer formed thereby, and a fuel cell separator. A method for coating metal according to an embodiment of the present invention includes preparing a metal base material; and forming a molten pool by irradiating a laser to a surface of the metal base material and forming a coating layer using an additive manufacturing by supplying a powder made of any one of Si, SiC, and a mixture of Cr and Al to the molten pool.

公开(公告)号：US09202597B2

公开(公告)日：2015-12-01

申请号：US13747614

申请日：2013-01-23

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

Inventor： Jeong-Yong Park ,  Byoung-Kwon Choi ,  Hyun Gil Kim ,  Sang Yoon Park ,  Yang-Il Jung ,  Dong Jun Park ,  Yang-Hyun Koo

IPC: C22C16/00 ,  G21C3/07 ,  G21C21/10 ,  C22F1/18

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 corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 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 total amount of the niobium, the iron and the chromium is 1.1 to 1.2 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 feasibility and safety.

Abstract translation: 公开了一种通过减少合金元素量的具有良好耐腐蚀性的核燃料包层锆合金，以及使用该锆合金制备锆合金核燃料包层的方法。 锆合金含有0.2〜0.5重量％的铌（Nb）; 0.2〜0.6重量％的铁（Fe）; 0.3〜0.5重量％的铬（Cr）; 0.1〜0.15重量％的氧（O）; 硅（Si）0.008〜0.012重量％，锆（Zr）余量。 铌，铁和铬的总量为1.1〜1.2重量％。 可以在事故条件和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，从而提高经济可行性和安全性。

公开(公告)号：US09136023B2

公开(公告)日：2015-09-15

申请号：US13747614

申请日：2013-01-23

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

Inventor： Jeong-Yong Park ,  Byoung-Kwon Choi ,  Hyun Gil Kim ,  Sang Yoon Park ,  Yang-Il Jung ,  Dong Jun Park ,  Yang-Hyun Koo

IPC: C22C16/00 ,  G21C3/07 ,  G21C21/10 ,  C22F1/18

Abstract: Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 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 total amount of the niobium, the iron and the chromium is 1.1 to 1.2 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 feasibility and safety.

公开(公告)号：US09099205B2

公开(公告)日：2015-08-04

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-Il Jung ,  Dong Jun Park ,  Yang-Hyun Koo

IPC: C22F1/18 ,  C22C16/00 ,  G21C3/07 ,  G21C21/10

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 (O); 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（O）; 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：US11118260B2

公开(公告)日：2021-09-14

申请号：US16762247

申请日：2018-11-14

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Jung Hwan Park ,  Hyun Gil Kim ,  Yang Il Jung ,  Dong Jun Park ,  Byoung Kwon Choi ,  Young Ho Lee ,  Jae Ho Yang

IPC: C23C14/00 ,  C23C14/16 ,  C23C14/32 ,  B32B15/01 ,  C22C16/00 ,  G21C3/07 ,  C23C14/24 ,  C23C14/22

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.

公开(公告)号：US09421740B2

公开(公告)日：2016-08-23

申请号：US13670515

申请日：2012-11-07

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

Inventor： Kun-Woo Song ,  Yang-Hyun Koo ,  Byoung-Kwon Choi ,  Il-Hyun Kim ,  Hyun-Gil Kim ,  Yang-Il Jung ,  Dong Jun Park ,  Jeong-Yong Park

IPC: C23C4/04 ,  C23C4/08 ,  C23C4/12 ,  B32B15/01 ,  C23C4/18 ,  C23C4/02 ,  C22C16/00 ,  C22F1/18 ,  G21C3/07 ,  G21C3/30

CPC classification number: B32B15/01 ,  C22C16/00 ,  C22F1/186 ,  C23C4/02 ,  C23C4/08 ,  C23C4/134 ,  C23C4/18 ,  G21C3/07 ,  G21C3/30 ,  Y02E30/40 ,  Y10T428/12674 ,  Y10T428/12812

Abstract: A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved.

Abstract translation: 提供了用于核燃料组件的锆合金，其提供增加的抗氧化和腐蚀性，并且还改善了与母体材料的接合，因为诸如硅（Si）或铬（Cr）的纯金属材料被均匀地涂覆在 母材通过等离子喷涂。 由于用于在锆合金上涂覆纯金属材料的等离子体喷涂不需要真空设备，并且由于涂覆产品的形状也不受限制，因此当将组分的表面均匀地处理如4 m形管子或间隔手柄装置，其形状非常复杂。 此外，由于涂覆的锆合金在事故和正常使用条件下在紧急情况下具有优异的抗氧化和耐腐蚀性，因此提高了核燃料的经济性和安全性。

公开(公告)号：US10808307B2

公开(公告)日：2020-10-20

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 ,  C22C1/02 ,  C22C27/06 ,  C23C4/08 ,  C22C16/00 ,  C22C19/03

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：US09111650B2

公开(公告)日：2015-08-18

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-Il Jung ,  Hyun Gil Kim ,  Byoung-Kwon Choi ,  Sang Yoon Park ,  Dong Jun Park ,  Yang-Hyun Koo

IPC: G21C3/07 ,  C22C16/00 ,  G21C21/10 ,  C22F1/18

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：US20130302639A1

公开(公告)日：2013-11-14

申请号：US13670515

申请日：2012-11-07

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

Inventor： Kun-Woo Song ,  Yang-Hyun Koo ,  Byoung-Kwon Choi ,  Il-Hyun Kim ,  Hyun-Gil Kim ,  Yang-Il Jung ,  Dong Jun Park ,  Jeong-Yong Park

IPC: B32B15/01 ,  C23C4/12 ,  C23C4/08

CPC classification number: B32B15/01 ,  C22C16/00 ,  C22F1/186 ,  C23C4/02 ,  C23C4/08 ,  C23C4/134 ,  C23C4/18 ,  G21C3/07 ,  G21C3/30 ,  Y02E30/40 ,  Y10T428/12674 ,  Y10T428/12812

Abstract: A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved.

Abstract translation: 提供了用于核燃料组件的锆合金，其提供增加的抗氧化和腐蚀性，并且还改善了与母体材料的接合，因为诸如硅（Si）或铬（Cr）的纯金属材料被均匀地涂覆在 母材通过等离子喷涂。 由于用于在锆合金上涂覆纯金属材料的等离子体喷涂不需要真空设备，并且由于涂覆产品的形状也不受限制，因此当将组分的表面均匀地处理如4 m形管子或间隔手柄装置，其形状非常复杂。 此外，由于涂覆的锆合金在事故和正常使用条件下在紧急情况下具有优异的抗氧化和耐腐蚀性，因此提高了核燃料的经济性和安全性。