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：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。

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：US06325966B1

公开(公告)日：2001-12-04

申请号：US09293099

申请日：1999-04-16

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

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

IPC分类号： C22C1600

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 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 in a range of 0.15 to 0.25 wt. %; tin in a range of 1.10 to 1.40 wt. %; iron in a range of 0.35 to 0.45; chromium in a range of 0.15 to 0.25; one element selected from the group consisting of molybdenum, copper and manganese in a range of 0.08 to 0.12 wt. %; oxygen in a range of 0.10 to 0.14 wt. %; and the balance being zirconium.

摘要翻译： 本文提出的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反应堆堆芯中的燃料棒包层，间隔栅格和结构部件。本发明的锆合金具有优异的腐蚀性 电阻和高强度包括如下的合金组成：铌在0.15至0.25wt。 ％; 锡在1.10至1.40重量％的范围内。 ％; 铁在0.35至0.45的范围内; 在0.15至0.25的范围内的铬; 一种元素选自钼，铜和锰，其含量范围为0.08至0.12wt。 ％; 0.10〜0.14重量％的氧。 ％; 余量为锆。

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：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）。

公开(公告)号：US11654474B2

公开(公告)日：2023-05-23

申请号：US16401394

申请日：2019-05-02

申请人： Youn Ho Jung ,  Jae Woong Jung

发明人： Youn Ho Jung ,  Jae Woong Jung ,  Yoon Sang Shin

IPC分类号： B21F23/00 ,  B21F1/02

CPC分类号： B21F23/00 ,  B21F1/02

摘要： A wire feeding unit includes a driving motor; a driving roller which rotates by a driving force of the driving motor; a plurality of driven rollers arranged such that outer circumferential surfaces thereof are positioned on a same line; a belt which interlocks the driving roller and the plurality of driven rollers and is brought into contact with a wire, which is drawn into a side of the driven rollers, on a side of the plurality of driven rollers; and a plurality of idlers which support the wire on a side in which the wire and the belt are in contact with each other and assist feeding of the wire along a feeding direction of the belt in a free-rotation state.

公开(公告)号：US06807246B1

公开(公告)日：2004-10-19

申请号：US10328974

申请日：2002-12-24

申请人： Dae Ho Kim ,  Kee Nam Song ,  Tae Hyun Chun ,  Kyung Ho Yoon ,  Dong Seok Oh ,  Heung Seok Kang ,  Youn Ho Jung ,  Hyung Kyu Kim ,  Wang Kee In ,  Chang-Hwan Shin ,  Gyung Jin Park

发明人： Dae Ho Kim ,  Kee Nam Song ,  Tae Hyun Chun ,  Kyung Ho Yoon ,  Dong Seok Oh ,  Heung Seok Kang ,  Youn Ho Jung ,  Hyung Kyu Kim ,  Wang Kee In ,  Chang-Hwan Shin ,  Gyung Jin Park

IPC分类号： G21C334

CPC分类号： G21C3/352 ,  G21C3/3563 ,  G21Y2002/201 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/40

摘要： A lips-type multi-purposed spacer grid for supporting fuel rods within a nuclear fuel assembly is disclosed. In the spacer grid, the fuel rods are in contact with dimples and water strider-type springs in an equiangular surface contact manner. The spacer grid distributes load, applied to the springs, to the entire structure of its inner strips, thus reducing peak stress at the contact surfaces between the fuel rods and the springs and diminishing vibration of the fuel rods, and thereby reducing possible fretting wear of the fuel rods due to hydraulic vibration of the fuel rods. The spacer grid also enlarges the allowable elastic range of the springs, and allows the springs to soundly support the fuel rods by using residual spring force. The spacer grid has mixing blades capable of minimizing pressure loss and flow interference, so that the fuel rod cooling efficiency of the nuclear fuel assembly is improved.

摘要翻译： 公开了一种用于在核燃料组件内支撑燃料棒的唇形多用间隔栅格。 在间隔网格中，燃料棒以等角面接触的方式接触凹坑和水刺式弹簧。 间隔栅格将施加到弹簧的负载分配到其内部条的整个结构，从而减少燃料棒和弹簧之间的接触表面处的峰值应力，并减少燃料棒的振动，从而减少可能的微动磨损 由于燃料棒的液压振动引起的燃料棒。 间隔网格也扩大了弹簧的允许弹性范围，并允许弹簧通过使用残余弹簧力来牢固地支撑燃料棒。 间隔栅格具有能够最小化压力损失和流动干扰的混合叶片，从而提高了核燃料组件的燃料棒冷却效率。

公开(公告)号：US07485246B2

公开(公告)日：2009-02-03

申请号：US11049452

申请日：2005-02-02

申请人： Young Woo Rhee ,  Keon Sik Kim ,  Jong Hun Kim ,  Ki Won Kang ,  Jae Ho Yang ,  Kun Woo Song ,  Youn Ho Jung

发明人： Young Woo Rhee ,  Keon Sik Kim ,  Jong Hun Kim ,  Ki Won Kang ,  Jae Ho Yang ,  Kun Woo Song ,  Youn Ho Jung

IPC分类号： G21C21/00

CPC分类号： G21C21/02 ,  C22B1/2413 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2004/40

摘要： A method for fabricating a sintered duplex nuclear fuel pellet includes the steps of: preparing a first powder composed of a material selected from the group consisting of UO2 and UO2—Er2O3, and a second powder composed of UO2—Gd2O3 and a sintering additive; producing a duplex compact consisting of an annular outer portion composed of the first powder and a cylindrical inner portion composed of the second powder; and sintering the duplex compact under a reducing gas atmosphere, wherein the sintering additive contains manganese of 0.001% to 2% by weight based on the total weight of the cylindrical inner portion.

摘要翻译： 一种烧结双相核燃料颗粒的制造方法包括以下步骤：制备由选自UO2和UO2-Er2O3的材料组成的第一粉末和由UO2-Gd2O3和烧结添加剂组成的第二粉末; 制造由第一粉末组成的环形外部部分和由第二粉末组成的圆筒形内部组成的双相压实体; 并在还原气体气氛下烧结所述双相压块，其中所述烧结添加剂含有基于所述圆筒形内部部分的总重量为0.001重量％至2重量％的锰。

公开(公告)号：US06881376B2

公开(公告)日：2005-04-19

申请号：US10677681

申请日：2003-10-02

申请人： Kun Woo Song ,  Jae Ho Yang ,  Keon Sik Kim ,  Ki Won Kang ,  Jong Hun Kim ,  Youn Ho Jung

发明人： Kun Woo Song ,  Jae Ho Yang ,  Keon Sik Kim ,  Ki Won Kang ,  Jong Hun Kim ,  Youn Ho Jung

IPC分类号： G21C3/62 ,  B22F3/00

CPC分类号： G21C3/623 ,  G21Y2002/104 ,  G21Y2004/10 ,  Y02E30/38

摘要： The present invention relates to a nuclear fuel body comprising tungsten network and a method for manufacturing the same, more particularly, a nuclear fuel body in which tungsten network is continuously formed over the entire or some parts of a sintered body and a method for manufacturing the same. The sintered body in the nuclear fuel body of the present invention contains tungsten network having excellent heat conductivity, leading to the enhancement of heat conductivity of the nuclear fuel sintered body itself with decreasing the temperature of the nuclear fuel, so that it can contribute to the improvement in safety and performance of nuclear fuel.

摘要翻译： 本发明涉及一种包括钨网络的核燃料体及其制造方法，更具体地说，涉及在烧结体的全部或部分上连续形成钨网的核燃料体， 相同。 本发明的核燃料体中的烧结体含有具有优异导热性的钨网络，导致核燃料烧结体本身的导热性随着核燃料温度的降低而提高，从而可以有助于 提高核燃料的安全和性能。