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：US20120145287A1

公开(公告)日：2012-06-14

申请号：US12392697

申请日：2009-02-25

申请人： Hyun Gil Kim ,  Yong Hwan Jeong ,  Byoung Kwon Choi ,  Sang Yoon Park ,  Myung Ho Lee ,  Jeong Yong Park ,  Jun Hwan Kim

发明人： Hyun Gil Kim ,  Yong Hwan Jeong ,  Byoung Kwon Choi ,  Sang Yoon Park ,  Myung Ho Lee ,  Jeong Yong Park ,  Jun Hwan Kim

IPC分类号： C22F1/18 ,  C22C16/00

CPC分类号： C22C16/00

摘要： Disclosed herein are a zirconium alloy composition, which exhibits excellent corrosion resistance by varying the kinds of metal oxides and controlling the size of precipitates of the composition, including: 1.05˜1.45 wt % of Nb; one or more selected from the group consisting of 0.1˜0.7 wt % of Fe and 0.05˜0.6 wt % of Cr; and residual Zr, and a method of preparing the same. The zirconium alloy composition exhibits excellent corrosion resistance by controlling the kinds and amounts of the elements included in the zirconium alloy composition and the heat-treatment temperature and thus varying the kinds of metal oxides formed during an oxidation process and controlling the size of precipitates of the zirconium alloy, so that it can be usefully used as a raw material for nuclear fuel cladding tubes, spacer grids, nuclear reactor internals and the like of a light-water reactor or a heavy-water reactor in a nuclear power plant.

摘要翻译： 本发明公开了一种锆合金组合物，其通过改变金属氧化物的种类和控制组合物的析出物的尺寸来表现出优异的耐腐蚀性，包括：1.05〜1.45重量％的Nb; 选自由0.1〜0.7重量％的Fe和0.05〜0.6重量％的Cr组成的组中的一种或多种; 和残余Zr，及其制备方法。 锆合金组合物通过控制包含在锆合金组合物中的元素的种类和数量以及热处理温度，从而改变氧化过程中形成的金属氧化物的种类和控制沉淀物的尺寸，显示出优异的耐腐蚀性 锆合金，因此可以有效地用作核电厂的轻水反应堆或重水反应堆的核燃料包层管，间隔栅格，核反应堆内部等的原料。

公开(公告)号：US20080192880A1

公开(公告)日：2008-08-14

申请号：US11734288

申请日：2007-04-12

申请人： Yong Hwan Jeong ,  Hyun Gil Kim ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Jong Hyuk Baek ,  Jeong Yong Park ,  Jun Hwan Kim

发明人： Yong Hwan Jeong ,  Hyun Gil Kim ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Jong Hyuk Baek ,  Jeong Yong Park ,  Jun Hwan Kim

IPC分类号： G21C3/07

CPC分类号： G21C3/07 ,  Y02E30/40

摘要： A high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof. Specifically, disclosed are a high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof, the composition comprising: 0.5-1.0 wt % iron; 0.25-0.5 wt % chromium; 0.06-0.18 wt % oxygen; at least one element selected from the group consisting of 0.2-0.5 wt % tin, 0.1-0.3 wt % niobium and 0.05-0.3 wt % copper; and the balance of zirconium. The zirconium alloy has excellent corrosion resistance, and thus can be used as a material for nuclear fuel claddings, spacer grids and nuclear reactor core structures in light water reactor and heavy water reactor nuclear power plants.

摘要翻译： 具有优异耐腐蚀性的高含铁锆组合物及其制备方法。 具体地，公开了具有优异耐腐蚀性的高含铁锆组合物及其制备方法，所述组合物包含：0.5-1.0重量％的铁; 0.25-0.5重量％铬; 0.06-0.18重量％氧气; 选自由0.2-0.5重量％锡，0.1-0.3重量％铌和0.05-0.3重量％铜组成的组中的至少一种元素; 和锆的平衡。 锆合金具有优异的耐腐蚀性，因此可用作轻水反应堆和重水反应堆核电站中核燃料包层，间隔栅格和核反应堆核心结构的材料。

公开(公告)号：US08070892B2

公开(公告)日：2011-12-06

申请号：US11734288

申请日：2007-04-12

申请人： Yong Hwan Jeong ,  Hyun Gil Kim ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Jong Hyuk Baek ,  Jeong Yong Park ,  Jun Hwan Kim

发明人： Yong Hwan Jeong ,  Hyun Gil Kim ,  Sang Yoon Park ,  Myung Ho Lee ,  Byoung Kwon Choi ,  Jong Hyuk Baek ,  Jeong Yong Park ,  Jun Hwan Kim

IPC分类号： C22C16/00 ,  C22F1/18

CPC分类号： G21C3/07 ,  Y02E30/40

摘要： A high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof. Specifically, disclosed are a high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof, the composition comprising: 0.5-1.0 wt % iron; 0.25-0.5 wt % chromium; 0.06-0.18 wt % oxygen; at least one element selected from the group consisting of 0.2-0.5 wt % tin, 0.1-0.3 wt % niobium and 0.05-0.3 wt % copper; and the balance of zirconium. The zirconium alloy has excellent corrosion resistance, and thus can be used as a material for nuclear fuel claddings, spacer grids and nuclear reactor core structures in light water reactor and heavy water reactor nuclear power plants.

摘要翻译： 具有优异耐腐蚀性的高含铁锆组合物及其制备方法。 具体地，公开了具有优异耐腐蚀性的高含铁锆组合物及其制备方法，所述组合物包含：0.5-1.0重量％的铁; 0.25-0.5重量％铬; 0.06-0.18重量％氧气; 选自由0.2-0.5重量％锡，0.1-0.3重量％铌和0.05-0.3重量％铜组成的组中的至少一种元素; 和锆的平衡。 锆合金具有优异的耐腐蚀性，因此可用作轻水反应堆和重水反应堆核电站中核燃料包层，间隔栅格和核反应堆核心结构的材料。

公开(公告)号：US20080131306A1

公开(公告)日：2008-06-05

申请号：US11734318

申请日：2007-04-12

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Myung Ho Lee ,  Sang Yoon Park ,  Jeong Yong Park ,  Jun Hwan Kim ,  Hyun Gil Kim

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Myung Ho Lee ,  Sang Yoon Park ,  Jeong Yong Park ,  Jun Hwan Kim ,  Hyun Gil Kim

IPC分类号： C22C16/00 ,  C22F1/16

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

摘要： The present invention relates to a zirconium alloy composition having excellent corrosion resistance for nuclear applications and a method of preparing the same. The zirconium alloy composition having excellent corrosion resistance for nuclear applications includes 1.3˜2.0 wt % of niobium, 0.05˜0.18 wt % of iron, 0.008˜0.012 wt % of silicon, 0.008˜0.012 wt % of carbon, and 0.1˜0.16 wt % of oxygen, with the balance being zirconium, or includes 2.8˜3.5 wt % of niobium, 0.2˜0.7 wt % of at least one of iron and copper, 0.008˜0.012 wt % of silicon, 0.008˜-0.012 wt % of carbon, and 0.1˜0.16 wt % of oxygen, with the balance being zirconium. The zirconium alloy composition according to the present invention, in which the amount of niobium, acting as a first alloying element, and the amount of at least one of iron and copper, acting as a second alloying element, are appropriately controlled, and silicon, carbon and oxygen are added in appropriate amounts, can exhibit excellent corrosion resistance, and thus can be usefully used as materials for nuclear fuel cladding tubes, support ribs, and core components of light water reactors and heavy water reactors.

摘要翻译： 本发明涉及对核应用具有优异的耐腐蚀性的锆合金组合物及其制备方法。 对于核应用具有优异的耐腐蚀性的锆合金组合物包括铌的1.3〜2.0重量％，铁的0.05〜0.18重量％，硅的0.008〜0.012重量％，碳的0.008〜0.012重量％和碳0.1〜0.16重量％ 的氧，余量为锆，或包含2.8〜3.5重量％的铌，0.2〜0.7重量％的铁和铜中的至少一种，0.008〜0.012重量％的硅，0.008〜-0.12重量％的碳， 和0.1〜0.16重量％的氧，余量为锆。 根据本发明的锆合金组合物，其中适当地控制充当第一合金元素的铌的量和用作第二合金元素的铁和铜中的至少一种的量，硅， 以适当的量添加碳和氧，可以表现出优异的耐腐蚀性，因此可以有效地用作核燃料包覆管，支撑肋和轻水反应堆和重水反应堆的核心部件的材料。

公开(公告)号：US06902634B2

公开(公告)日：2005-06-07

申请号：US10193494

申请日：2002-07-09

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Sang Yoon Park ,  Myung Ho Lee ,  Cheol Nam ,  Jeong Yong Park ,  Youn Ho Jung

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Sang Yoon Park ,  Myung Ho Lee ,  Cheol Nam ,  Jeong Yong Park ,  Youn Ho Jung

IPC分类号： G21C3/06 ,  B21J5/00 ,  C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/07

CPC分类号： C22C16/00 ,  C22F1/186 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  Y02E30/40

摘要： The present invention relates to a method for manufacturing zirconium-based alloys containing niobium with superior corrosion resistance for use in nuclear fuel rod claddings. The method of this invention comprises melting of the alloy, β-forging, β-quenching, hot-working, vacuum annealing, cold-working, intermediate annealing and final annealing, whereby the niobium concentration in the α-Zr matrix decreases from the supersaturation state to the equilibrium state to improve the corrosion resistance of the alloy. Such zirconium-based alloys containing niobium are usefully applied to nuclear fuel rod cladding of the cores in light water reactors and heavy water reactors.

摘要翻译： 本发明涉及一种用于核燃料棒包层的含有优良耐腐蚀性的含有铌的锆基合金的方法。 本发明的方法包括熔化合金，β-锻造，β-淬火，热加工，真空退火，冷加工，中间退火和最终退火，由此α-Zr基体中的铌浓度从过饱和度 状态到平衡状态，以提高合金的耐腐蚀性。 这种含有铌的锆基合金可用于轻水反应堆和重水反应堆中核心的核燃料棒包层。

公开(公告)号：US06514360B2

公开(公告)日：2003-02-04

申请号：US09852953

申请日：2001-05-10

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Kyeong Ho Kim ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Younho Jung

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Kyeong Ho Kim ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Younho Jung

IPC分类号： C22F118

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

摘要： Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at &bgr; phase range; &bgr;-quenching the forged ingot after solution heat-treatment at 1015-1075° C.; hot-working the quenched ingot at 600-650° C.; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600° C., wherein temperatures of intermediate vacuum annealing and final vacuum annealing after &bgr;-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (&Sgr; A) is limited to 1.0×10−18 hr or lower.

摘要翻译： 公开了一种制造用于高燃耗核燃料的含铌锆合金管和一片材的方法。 该方法包括将Nb添加的锆合金熔化成锭; 在β相范围锻造锭; 在1015-1075°C固溶热处理后，对锻造锭进行β淬火淬火。 在600-650℃下对淬火锭进行热加工; 用三到五道次热处理热加工铸锭，中间真空退火; 在440-600℃下对冷加工锭进行最终真空退火，其中改变了中间真空退火和β淬火后的最终真空退火的温度，以达到将合金基体中的析出物限制在 平均直径为80nm以下，累积退火参数（SIGMA A）为1.0×10-18hr以下。

公开(公告)号：US06261516B1

公开(公告)日：2001-07-17

申请号：US09521645

申请日：2000-03-08

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Kyeong Ho Kim ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Youn Ho Jung

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Kyeong Ho Kim ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Youn Ho Jung

IPC分类号： C22C1600

CPC分类号： C22C16/00 ,  G21C3/07 ,  Y02E30/40

摘要： The invention presented herein relates to a niobium-containing zirconium alloy for use in nuclear fuel cladding. The Zr alloy of this invention with superior corrosion resistance is characterized as comprising an alloy composition as follows: 1) niobium (Nb), in a range of 0.8 to 1.2 wt. %; one or more elements selected from the group consisting of iron (Fe), molybdenum (Mo), copper (Cu) and manganese (Mn), in a range of 0.1 to 0.3 wt. %, respectively; oxygen (O), in a range of 600 to 1400 ppm; silicon (Si), in a range of 80 to 120 ppm; and the balance being of Zr, 2) Nb, in a range of 1.3 to 1.8 wt. %; tin (Sn), in a range of 0.2 to 0.5 wt. %; one element selected from the group consisting of Fe, Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr, 3) Nb, in a range of 1.3 to 1.8 wt. %; Sn, in a range of 0.2 to 0.5 wt. %; Fe, in a range of 0.1 to 0.3 wt. %; one element selected from the group consisting of chromium (Cr), Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr, and 4) Nb, in a range of 0.3 to 1.2 wt. %; Sn, in a range of 0.4 to 1.2 wt. %; Fe, in a range of 0.1 to 0.5 wt. %; one element selected from the group consisting of Mo, Cu and Mn, in a range of 0.1 to 0.3 wt. %; O, in a range of 600 to 1400 ppm; Si, in a range of 80 to 120 ppm; and the balance being of Zr.

摘要翻译： 本文提出的本发明涉及用于核燃料包层的含铌锆合金。 具有优异耐腐蚀性的本发明的Zr合金的特征在于包括如下的合金组成：1）铌（Nb）在0.8〜1.2重量％的范围内。 ％; 选自铁（Fe），钼（Mo），铜（Cu）和锰（Mn））中的一种或多种元素在0.1至0.3重量％的范围内。 ％， 分别; 氧（O），在600〜1400ppm的范围内; 硅（Si），在80〜120ppm的范围内; 余量为Zr，2）Nb，为1.3〜1.8重量％。 ％; 锡（Sn）的范围为0.2〜0.5重量％。 ％; 选自Fe，Mo，Cu和Mn中的一种元素，在0.1至0.3重量％的范围内。 ％; O，在600〜1400ppm的范围内; Si，在80〜120ppm的范围内; 余量为Zr，3）Nb，在1.3〜1.8重量％的范围内。 ％; Sn，在0.2〜0.5重量％的范围内。 ％; Fe在0.1〜0.3重量％的范围内。 ％; 选自铬（Cr），Mo，Cu和Mn中的一种元素在0.1至0.3重量％的范围内。 ％; O，在600〜1400ppm的范围内; Si，在80〜120ppm的范围内; 其余为Zr，4）Nb为0.3〜1.2wt。 ％; Sn，在0.4〜1.2重量％的范围内。 ％; Fe在0.1〜0.5重量％的范围内。 ％; 选自Mo，Cu和Mn中的一种元素在0.1至0.3重量％的范围内。 ％; O，在600〜1400ppm的范围内; Si，在80〜120ppm的范围内; 其余为Zr。

公开(公告)号：US06811746B2

公开(公告)日：2004-11-02

申请号：US10040743

申请日：2001-11-01

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Youn Ho Jung

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byoung Kwon Choi ,  Myung Ho Lee ,  Sang Yoon Park ,  Cheol Nam ,  Youn Ho Jung

IPC分类号： C22C1600

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

摘要： The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a=0.05-0.4 wt %, b=0.3-0.7 wt %, c=0.1-0.4 wt %, d=0-0.2 wt % and e=0.01-0.2 wt %, provided that Nb+Sn=0.35-1.0 wt %), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at &bgr; phase range, &bgr;-quenching the forged ingot at 1015-1075° C., hot-working the quenched ingot at 600-650° C., cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing and final vacuum annealing the worked ingot at 460-540° C., which can be applied to the core components in a light water and a heavy water atomic reactor type nuclear power plant.

摘要翻译： 本发明涉及具有优异的耐腐蚀性和机械性能的锆合金以及通过锆合金制备核燃料包层管的方法。 更具体地，本发明涉及包含Zr-aNb-bSn-cFe-dCr-eCu（a = 0.05-0.4重量％，b = 0.3-0.7重量％，c = 0.1-0.4重量％，d = 0-0.2重量％，e = 0.01-0.2重量％，条件是Nb + Sn = 0.35-1.0重量％），以及制备锆合金核燃料包层管的方法，包括熔融金属混合物， 锆和合金元素以获得锭，在β相范围锻造锭，在1015-1075℃下对锻造锭进行β淬火，在600-650℃下热处理淬火锭，冷热处理， 在三到五道次的铸锭中进行中间真空退火和最终真空退火处理的锭在460-540℃，可以应用于轻水和重水原子反应堆型核电站的核心部件。