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：US6001326A

公开(公告)日：1999-12-14

申请号：US162009

申请日：1998-09-28

申请人： Sun-Jae Kim ,  Soon Dong Park ,  Kyeong Ho Kim ,  Yong Hwan Jeong ,  Il Hiun Kuk

发明人： Sun-Jae Kim ,  Soon Dong Park ,  Kyeong Ho Kim ,  Yong Hwan Jeong ,  Il Hiun Kuk

IPC分类号： C01G23/053 ,  C01G25/02 ,  C01G23/047

CPC分类号： C01G23/0536 ,  C01P2004/03 ,  C01P2004/52 ,  C01P2006/12

摘要： A method for production of mono-dispersed and crystalline titanium dioxide ultra fine powders comprises preparing an aqueous titanyl chloride solution, diluting the aqueous titanyl chloride solution to a concentration of between about 0.2 to 1.2 mole and heating the diluted aqueous titanyl chloride solution and maintaining the solution in a temperature range of between 15 to 155.degree. C. to precipitate titanium dioxide. The aqueous titanyl chloride solution is prepared by adding ice pieces of distilled water or icing distilled water to undiluted titanium tetrachloride.

摘要翻译： 制备单分散和结晶二氧化钛超细粉末的方法包括制备二氯氧化钛水溶液，将氯化钛水溶液稀释至约0.2至1.2摩尔的浓度，并加热稀释的氯化钛水溶液并保持 溶液在15至155℃的温度范围内以沉淀二氧化钛。 通过向未稀释的四氯化钛中加入蒸馏水或结冰蒸馏水的冰块来制备二氯化钛水溶液。

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：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：US5985211A

公开(公告)日：1999-11-16

申请号：US96660

申请日：1998-06-12

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byong Kwon Choi ,  Kyeong Ho Kim ,  Sun Jae Kim ,  Youn Ho Jung ,  Il Hiun Kuk

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byong Kwon Choi ,  Kyeong Ho Kim ,  Sun Jae Kim ,  Youn Ho Jung ,  Il Hiun Kuk

IPC分类号： C22C16/00

CPC分类号： C22C16/00

摘要： The present invention is directed to an advanced zirconium alloy having superior corrosion resistance and high strength suitable for fuel rod cladding, spacer grids and other structural components in a reactor core of nuclear power plants.

摘要翻译： 本发明涉及一种具有优异的耐腐蚀性和高强度的先进的锆合金，适用于核电站的反应堆核心中的燃料棒包层，间隔栅格和其他结构部件。

公开(公告)号：US08786303B2

公开(公告)日：2014-07-22

申请号：US12858673

申请日：2010-08-18

申请人： Kab Yong Kim ,  Hyun Soon Jang ,  Yong Hwan Jeong

发明人： Kab Yong Kim ,  Hyun Soon Jang ,  Yong Hwan Jeong

IPC分类号： G01R1/067 ,  G01R31/28

CPC分类号： G01R31/2891 ,  G01R31/2884

摘要： A semiconductor device includes a plurality of sensor pads configured to receive a probe signal from a testing apparatus, and a plurality of normal pads configured to receive a driving signal to drive the semiconductor device. In the plurality of sensor pads and the plurality of normal pads, a length in a direction corresponding to one of progress directions of a plurality of needles of the testing apparatus is longer than a length in another progress direction of the plurality of needles.

摘要翻译： 半导体器件包括被配置为从测试装置接收探测信号的多个传感器焊盘以及被配置为接收驱动信号以驱动半导体器件的多个正常焊盘。 在多个传感器焊盘和多个正常焊盘中，与测试装置的多个针的进给方向之一相对应的方向上的长度比多个针的另一个进给方向上的长度长。

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：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：US5972288A

公开(公告)日：1999-10-26

申请号：US96659

申请日：1998-06-12

申请人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byong Kwon Choi ,  Kyeong Ho Kim ,  Sun Jae Kim ,  Youn Ho Jung ,  Il Hiun Kuk

发明人： Yong Hwan Jeong ,  Jong Hyuk Baek ,  Byong Kwon Choi ,  Kyeong Ho Kim ,  Sun Jae Kim ,  Youn Ho Jung ,  Il Hiun Kuk

IPC分类号： C22C16/00

CPC分类号： C22C16/00

摘要： The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components as used in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows:niobium(Nb), in a range of 0.05 to 0.3 wt. %;tin(Sn), in a range of 0.8 to 1.6 wt. %;iron(Fe), in a range of 0.2 to 0.4 wt. %;a selected one from the group consisted of vanadium(V), tellurium(Te), antimony(Sb), molybdenum(Mo), tantalum(Ta), and copper(Cu), in a range of 0.05 to 0.20 wt. %;oxygen(O), in a range of 600 to 1400 ppm; andthe balance being zirconium(Zr).

摘要翻译： 本发明涉及一种具有优良耐腐蚀性和高强度的锆合金，用于轻水和重水核电厂的反应堆堆芯中所用的燃料棒包层，间隔栅格和结构部件。 具有优异的耐腐蚀性和高强度的本发明的锆合金包括如下的合金组成：铌（Nb）在0.05至0.3重量％的范围内。 ％; 锡（Sn）的范围为0.8〜1.6重量％。 ％; 铁（Fe），在0.2〜0.4重量％的范围内。 ％; 选自钒（V​​），碲（Te），锑（Sb），钼（Mo），钽（Ta）和铜（Cu）组成的组中的一种。 ％; 氧（O），在600〜1400ppm的范围内; 余量为锆（Zr）。