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：US20140185730A1

公开(公告)日：2014-07-03

申请号：US14060432

申请日：2013-10-22

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

Inventor： Keon-Sik KIM ,  Yang-Hyun KOO ,  Jong-Hun KIM ,  JangSoo OH ,  Young Woo RHEE ,  Dong-Joo KIM ,  Jae-Ho YANG

IPC: G21C3/04 ,  G21C3/16

CPC classification number: G21C3/044 ,  G21C3/16 ,  G21C3/17 ,  G21C3/58 ,  G21C3/62 ,  G21C21/02 ,  G21C2003/045 ,  Y02E30/38

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 μM (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract translation: 二氧化铀核燃料颗粒具有约50至约400微米（相对于三维尺寸），由具有化学吸引力的陶瓷材料形成，其具有在核燃料颗粒中产生的裂变产物以吸收和捕获裂变产物， 使得裂变产物的提取可以在正常操作条件下再培训，并且可以通过减轻PCI来提高核燃料的性能。 另外，具有大的发生量或长半衰期的Cs和I的高度放射性的裂变产物可以在事故状态下被捕获到颗粒中，而不会被外部释放。

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：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：US20160372215A1

公开(公告)日：2016-12-22

申请号：US14591498

申请日：2015-01-07

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Dong-Joo KIM ,  Young Woo RHEE ,  Keon-Sik KIM ,  Jong-Hun KIM ,  JangSoo OH ,  Jae-Ho YANG ,  Yang-Hyun KOO

IPC: G21C3/60 ,  G21C3/04 ,  G21C3/62

CPC classification number: G21C3/04 ,  G21C3/623 ,  G21C21/02 ,  G21C2003/045 ,  Y02E30/38

Abstract: A method of a nuclear fuel pellet including a thermal conductive metal and a nuclear fuel pellet prepared thereby. The method includes preparing an oxide nuclear fuel granule having about 30%-45% theoretical density, mixing the fuel granule with thermal conductive metal powder, compacting the fuel granule with which the thermal conductive metal powder is mixed to prepare a green pellet, and sintering the green pellet. In the method, the sintering may be performed under a reducing gas atmosphere that is the same as the commercial pellet preparing process. Thus, compatibility compared to existing commercial preparing processes may be superior. Also, since a liquefied oxide formation process and a reducing process are omitted, the distribution uniformity of the metal material within the pellet may be superior. Therefore, the nuclear fuel pellet in which the metal network and fine microstructure are uniformly distributed within the pellet may be prepared.

Abstract translation: 一种核燃料颗粒的方法，其包括由其制备的导热金属和核燃料颗粒。 该方法包括制备具有约30％-45％理论密度的氧化物核燃料颗粒，将燃料颗粒与导热金属粉末混合，压实混合导热金属粉末的燃料颗粒以制备生坯，并烧结 绿色颗粒。 在该方法中，可以在与商业颗粒制备方法相同的还原气体气氛下进行烧结。 因此，与现有的商业制备方法相比的兼容性可能是优越的。 此外，由于省略了液化氧化物形成工艺和还原工艺，所以颗粒内的金属材料的分布均匀性可以是优异的。 因此，可以制备其中金属网络和精细微结构均匀分布在颗粒内的核燃料颗粒。

公开(公告)号：US20140185731A1

公开(公告)日：2014-07-03

申请号：US14061662

申请日：2013-10-23

Applicant: Korea Atomic Energy Research Institute

Inventor： Keon-Sik KIM ,  Yang-Hyun KOO ,  Jong-Hun KIM ,  JangSoo OH ,  Young Woo RHEE ,  Dong-Joo KIM ,  Jae-Ho YANG

IPC: G21C3/04

CPC classification number: G21C3/044 ,  G21C3/17 ,  G21C3/58 ,  G21C21/02 ,  G21C2003/045 ,  Y02E30/38

Abstract: A uranium dioxide nuclear fuel pellet includes metallic microcells having a high protection capacity for fission products and a high thermal conductivity simultaneously arranged in the nuclear fuel pellet to trap fission products, such that extraction of fission products may be restrained in a normal operation condition and that the temperature of a nuclear fuel may be lowered to enhance the performance of the nuclear fuel, only to restrain extraction of radioactive fission products toward the environment in an accident condition to enhance a stability of the nuclear fuel pellet, and a fabricating method thereof.

Abstract translation: 二氧化铀核燃料颗粒包括对于裂变产物具有高保护能力的金属微细胞和同时布置在核燃料颗粒中的高热导率以捕获裂变产物，从而可以在正常操作条件下抑制裂变产物的提取，并且 可以降低核燃料的温度以提高核燃料的性能，只是为了在事故条件下抑制放射性裂变产物向环境的提取，以提高核燃料颗粒的稳定性及其制造方法。