公开(公告)号：US08444782B2

公开(公告)日：2013-05-21

申请号：US12612101

申请日：2009-11-04

申请人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

发明人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

IPC分类号： C21D8/00

CPC分类号： C21D8/1266 ,  C21D2211/004 ,  C21D2211/005 ,  C21D2211/008

摘要： Provided is a method of manufacturing a high strength ferritic/martensitic steel. The method includes melting a ferritic/martensitic steel, hot-working the melted ferritic/martensitic steel, normalizing the hot-worked ferritic/martensitic steel at a temperature of about 1050° C. to about 1200° C., tempering the ferritic/martensitic steel at a temperature of about 600° C. or less, and leaving MX precipitates while preventing a M23C6 precipitate from being precipitated, and cold-working and thermal-treating the ferritic/martensitic steel in a multistage fashion, and precipitating M23C6 precipitates. Through the above described configuration, the high strength ferritic/martensitic steel that prevents a ductility from being deteriorated even in a high-temperature environment may be manufactured.

摘要翻译： 提供一种制造高强度铁素体/马氏体钢的方法。 该方法包括熔化铁素体/马氏体钢，对熔融的铁素体/马氏体钢进行热加工，使热处理的铁素体/马氏体钢在约1050℃至约1200℃的温度下归一化，回火铁素体/马氏体 钢在约600℃以下，留下MX析出物，同时防止M23C6沉淀物析出，并对铁素体/马氏体钢进行多级冷加工和热处理，并析出M23C6沉淀物。 通过上述结构，可以制造即使在高温环境下也能够防止延展性劣化的高强度铁素体/马氏体钢。

公开(公告)号：US08155260B2

公开(公告)日：2012-04-10

申请号：US12110775

申请日：2008-04-28

申请人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

发明人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

IPC分类号： G21C3/00

CPC分类号： G21C3/20 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/40

摘要： Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

摘要翻译： 本文公开了一种用于快堆的核燃料棒及其制造方法，其包括形成在包层的内表面上的氧化物被覆层。 用于快堆的核燃料棒（包括形成在包层内表面上的氧化物涂层）可以增加快堆的金属燃料块的最大允许燃耗和最大允许温度，从而延长其在 快堆，从而提高经济效益。 此外，与现有的形成金属衬垫的方法相比，燃料棒的制造更简单，并且所公开的方法能够以简单和成本有效的方式制造燃料棒的包层。

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：US20090141851A1

公开(公告)日：2009-06-04

申请号：US12110775

申请日：2008-04-28

申请人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

发明人： Chan Bock Lee ,  Jong-Hyuk Baek ,  Byoung-Oon Lee ,  Jin-Sik Cheon ,  Ho Jin Ryu ,  Jun Hwan Kim ,  Sung Ho Kim ,  Tae-Kyu Kim ,  Woo-Gon Kim ,  Chong-Tak Lee ,  Ki-Hwan Kim ,  Young-Mo Ko ,  Yoon-Myeong Woo ,  Seok-Jin Oh ,  Dohee Hahn

IPC分类号： G21C3/07

CPC分类号： G21C3/20 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/303 ,  Y02E30/40

摘要： Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

摘要翻译： 本文公开了一种用于快堆的核燃料棒及其制造方法，其包括形成在包层的内表面上的氧化物被覆层。 用于快堆的核燃料棒（包括形成在包层内表面上的氧化物涂层）可以增加快堆的金属燃料块的最大允许燃耗和最大允许温度，从而延长其在 快堆，从而提高经济效益。 此外，与现有的形成金属衬垫的方法相比，燃料棒的制造更简单，并且所公开的方法能够以简单和成本有效的方式制造燃料棒的包层。

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：US09598750B2

公开(公告)日：2017-03-21

申请号：US13280585

申请日：2011-10-25

申请人： Sung Ho Kim ,  Jong Hyuk Baek ,  Tae Kyu Kim ,  Woo Gon Kim ,  Jun Hwan Kim ,  Chang Hee Han ,  Chan Bock Lee ,  Yeong-Il Kim ,  Dohee Hahn

发明人： Sung Ho Kim ,  Jong Hyuk Baek ,  Tae Kyu Kim ,  Woo Gon Kim ,  Jun Hwan Kim ,  Chang Hee Han ,  Chan Bock Lee ,  Yeong-Il Kim ,  Dohee Hahn

IPC分类号： C22C38/02 ,  C22C38/00 ,  C21D6/00 ,  C22C1/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

CPC分类号： C22C38/001 ,  C21D6/002 ,  C21D2211/005 ,  C21D2211/008 ,  C22C1/02 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

摘要： Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

公开(公告)号：US20120106693A1

公开(公告)日：2012-05-03

申请号：US13280585

申请日：2011-10-25

申请人： Sung Ho Kim ,  Jong Hyuk Baek ,  Tae Kyu Kim ,  Woo Gon Kim ,  Jun Hwan Kim ,  Chang Hee Han ,  Chan Bock Lee ,  Yeong-II Kim ,  Dohee Hahn

发明人： Sung Ho Kim ,  Jong Hyuk Baek ,  Tae Kyu Kim ,  Woo Gon Kim ,  Jun Hwan Kim ,  Chang Hee Han ,  Chan Bock Lee ,  Yeong-II Kim ,  Dohee Hahn

IPC分类号： G21C1/02 ,  C22C38/44 ,  G21C1/00 ,  C22C38/48 ,  C22C38/54 ,  C22C38/02 ,  C21D8/00 ,  C22C38/46

CPC分类号： C22C38/001 ,  C21D6/002 ,  C21D2211/005 ,  C21D2211/008 ,  C22C1/02 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  C22C38/46 ,  C22C38/48 ,  C22C38/54 ,  G21C1/02 ,  G21C3/07

摘要： Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with to superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

摘要翻译： 本文公开了一种高Cr铁素体/马氏体钢，其包含0.04至0.13重量％的碳，0.03至0.07重量％的硅，0.40至0.50重量％的锰，0.40至0.50重量％的镍，8.5至9.5 铬，0.45〜0.55重量％的钼，0.10〜0.25重量％的钒，0.02〜0.10重量％的钽，0.21〜0.25重量％的铌，1.5〜3.0重量％的钨 ，0.015〜0.025重量％的氮，0.01〜0.02重量％的硼和铁的平衡。 通过调节氮，合金元素含量，提供高Cr铁素体/马氏体钢，具有优异的抗拉强度和抗蠕变性，可以有效地用作钠冷快堆的核心成分材料（ SFR）。

公开(公告)号：US20100108207A1

公开(公告)日：2010-05-06

申请号：US12612101

申请日：2009-11-04

申请人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

发明人： Woo-Gon Kim ,  Chan-Bock Lee ,  Jong-Hyuk Baek ,  Do-Hee Hahn ,  Sung-Ho Kim ,  Chang-Hee Han ,  Tae-Kyu Kim ,  Jun-Hwan Kim

IPC分类号： C21D8/00

CPC分类号： C21D8/1266 ,  C21D2211/004 ,  C21D2211/005 ,  C21D2211/008

摘要： Provided is a method of manufacturing a high strength ferritic/martensitic steel. The method includes melting a ferritic/martensitic steel, hot-working the melted ferritic/martensitic steel, normalizing the hot-worked ferritic/martensitic steel at a temperature of about 1050° C. to about 1200° C., tempering the ferritic/martensitic steel at a temperature of about 600° C. or less, and leaving MX precipitates while preventing a M23C6 precipitate from being precipitated, and cold-working and thermal-treating the ferritic/martensitic steel in a multistage fashion, and precipitating M23C6 precipitates. Through the above described configuration, the high strength ferritic/martensitic steel that prevents a ductility from being deteriorated even in a high-temperature environment may be manufactured.

摘要翻译： 提供一种制造高强度铁素体/马氏体钢的方法。 该方法包括熔化铁素体/马氏体钢，对熔融的铁素体/马氏体钢进行热加工，使热处理的铁素体/马氏体钢在约1050℃至约1200℃的温度下归一化，回火铁素体/马氏体 钢在约600℃以下，留下MX析出物，同时防止M23C6沉淀物析出，并对铁素体/马氏体钢进行多级冷加工和热处理，并析出M23C6沉淀物。 通过上述结构，可以制造即使在高温环境下也能够防止延展性劣化的高强度铁素体/马氏体钢。

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。