公开(公告)号：US20130344348A1

公开(公告)日：2013-12-26

申请号：US13748214

申请日：2013-01-23

申请人： Yang-Hyun Koo ,  Byoung-Kwon Choi ,  Jeong-Yong Park ,  Il Hyun Kim ,  Yang-Il Jung ,  Dong Jun Park ,  Hyun Gil Kim

发明人： Yang-Hyun Koo ,  Byoung-Kwon Choi ,  Jeong-Yong Park ,  Il Hyun Kim ,  Yang-Il Jung ,  Dong Jun Park ,  Hyun Gil Kim

IPC分类号： G21C3/07 ,  B32B15/01 ,  B05D3/06

CPC分类号： G21C3/07 ,  B05D3/06 ,  B22F7/08 ,  B22F2999/00 ,  B23K26/32 ,  B23K26/34 ,  B23K35/005 ,  B23K35/365 ,  B32B15/01 ,  C22C16/00 ,  Y02E30/40 ,  Y02P10/295 ,  Y10T428/12063 ,  Y10T428/26 ,  B22F3/1055

摘要： A zirconium alloy with a coating layer formed on a surface comprising a mixed layer, the mixed layer comprises one or more very high temperature oxidation resistant material and zirconium alloy parent material selected from the group consisting of Y2O3, SiO2, ZrO2, Cr2O3, Al2O3, Cr3C2, SiC, ZrC, ZrN, Si and Cr, and in a vertical direction on a boundary between the mixed layer and the zirconium alloy parent material is formed a gradient of compositions between the very high temperature oxidation resistance material and the zirconium alloy parent material.

摘要翻译： 一种在包含混合层的表面上形成有涂层的锆合金，该混合层包括一种或多种非常耐高温的抗氧化材料和选自Y2O3，SiO2，ZrO2，Cr2O3，Al2O3， Cr3C2，SiC，ZrC，ZrN，Si和Cr，并且在混合层和锆合金母材之间的边界上的垂直方向上形成了极高耐氧化性材料和锆合金母体材料之间的组成梯度 。

公开(公告)号：US09346125B2

公开(公告)日：2016-05-24

申请号：US13763203

申请日：2013-02-08

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

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

IPC分类号： B23K26/00 ,  B23K26/08 ,  B23K26/12 ,  B23K26/32 ,  B23K35/30 ,  B23K35/32 ,  B23K35/02

CPC分类号： B23K26/354 ,  B23K26/083 ,  B23K26/123 ,  B23K26/144 ,  B23K26/32 ,  B23K26/342 ,  B23K35/0244 ,  B23K35/3033 ,  B23K35/3053 ,  B23K35/32 ,  B23K2103/02 ,  B23K2103/08 ,  B23K2103/26 ,  B23K2103/50 ,  C21D2211/004

摘要： An oxide dispersion strengthening (ODS) method of a metallic material using a laser is provided, which includes melting a surface of a metallic matrix placed on a movable stage by irradiating a laser onto the surface (step 1), supplying an oxide dispersion strengthening (ODS) powder at a site of the matrix surface which is melt at step 1 (step 2), and cooling the matrix in which the ODS powder is supplied at step 2 (step 3). Because oxide particles are directly supplied into previously-made sheet or tube matrix, fabrication process is simplified, fabrication cost is reduced, and end product is fabricated efficiently.

公开(公告)号：US20100108204A1

公开(公告)日：2010-05-06

申请号：US12435708

申请日：2009-05-05

申请人： Jeong-Yong Park ,  Yong Hwan Jeong ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Hyun Gil Kim ,  Yang Il Jung

发明人： Jeong-Yong Park ,  Yong Hwan Jeong ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Hyun Gil Kim ,  Yang Il Jung

IPC分类号： C22F1/18 ,  C22C16/00

CPC分类号： G21C3/07 ,  C22C16/00 ,  C22F1/186 ,  G21C21/02 ,  Y02E30/40

摘要： Disclosed herein is a zirconium alloy composition for nuclear fuel cladding tubes, comprising: 1.6˜2.0 wt % of Nb; 0.05˜0.14 wt % of Sn; 0.02˜0.2 wt % of one or more elements selected from the group consisting of Fe, Cr and Cu; 0.09˜0.15 wt % of O; 0.008˜0.012 wt % of Si; and a balance of Zr, a nuclear fuel cladding tube comprising the zirconium alloy composition, and a method of manufacturing the nuclear fuel cladding tube. Since the nuclear fuel cladding tube made of the zirconium alloy composition can maintain excellent corrosion resistance by forming a protective oxide film thereon under the conditions of high-temperature and high-pressure cooling water and water vapor, it can be usefully used as a nuclear fuel cladding tube for light water reactors or heavy water reactors, thus improving the economical efficiency and safety of the use of nuclear fuel.

摘要翻译： 本发明公开了一种用于核燃料包覆管的锆合金组合物，其包含：1.6〜2.0重量％的Nb; 0.05〜0.14重量％的Sn; 0.02〜0.2重量％的选自Fe，Cr和Cu中的一种或多种元素; 0.09〜0.15重量％的O; 0.008〜0.012重量％的Si; 余量为Zr，包含锆合金组合物的核燃料包层管，以及核燃料包壳管的制造方法。 由于由锆合金组成的核燃料包覆管可以在高温高压冷却水和水蒸气的条件下通过在其上形成保护性氧化膜来保持优异的耐腐蚀性，因此可以有效地用作核燃料 用于轻水反应堆或重水反应堆的包层管，从而提高使用核燃料的经济效益和安全性。

公开(公告)号：US20100322370A1

公开(公告)日：2010-12-23

申请号：US12770131

申请日：2010-04-29

申请人： Hyun Gil Kim ,  Yong-Hwan Jeong ,  Sang-Yoon Park ,  Byoung-Kwon Choi ,  Jeong-Yong Park ,  Yang-II Jung ,  Dong-Jun Park

发明人： Hyun Gil Kim ,  Yong-Hwan Jeong ,  Sang-Yoon Park ,  Byoung-Kwon Choi ,  Jeong-Yong Park ,  Yang-II Jung ,  Dong-Jun Park

IPC分类号： G21C3/06 ,  C22F1/18

CPC分类号： G21C21/00 ,  C22C16/00 ,  C22F1/18 ,  C22F1/186 ,  G21C3/07 ,  G21C21/02 ,  Y02E30/40

摘要： A process of manufacturing zirconium alloy. The process may be used to make a nuclear fuel guide tube and/or a measuring tube which are main components of a nuclear fuel assembly structure. While a nuclear fuel guide tube and a measuring tube are manufactured by performing three-step cold working, and intermediate and final thermal annealing from a semi-finished TREX shell in the conventional method, the present invention relates to zirconium alloy undergoing two-step cold working, and intermediate and final thermal annealing from a TREX shell, resulting in enhanced strength and corrosion resistance. The present invention may be applied to a nuclear fuel guide tube and a measuring tube used for a nuclear fuel assembly in a light water nuclear reactor because, by the shortened process, high percentage reduction in thickness between processes and an decrease in thermal annealing time may sustain high strength and excellent corrosion resistance, and achieve economy of manufacture by reducing the number of processes.

摘要翻译： 制造锆合金的工艺。 该方法可用于制造核燃料组件结构的主要组分的核燃料导管和/或测量管。 通过以往的方法，通过进行三步骤冷加工和半成品TREX壳体的中间和最终热退火来制造核燃料导向管和测量管，本发明涉及经历两步冷却的锆合金 工作，以及TREX外壳的中间和最终热退火，从而提高强度和耐腐蚀性。 本发明可以应用于用于轻水核反应堆中的核燃料组件的核燃料导管和测量管，因为通过缩短的过程，工艺之间厚度的高百分比减少和热退火时间的降低可以 保持高强度和优异的耐腐蚀性，通过减少工艺数量实现制造经济。