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1. 发明申请

US20120106693A1 HIGH Cr FERRITIC/MARTENSITIC STEELS HAVING AN IMPROVED CREEP RESISTANCE FOR IN-CORE COMPONENT MATERIALS IN NUCLEAR REACTOR, AND PREPARATION METHOD THEREOF 有权
标题翻译：对核反应堆中的核心组分材料具有改进的耐腐蚀性能的高铬/马氏体钢及其制备方法
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）。

2. 发明申请

US20110162764A1 HIGH-CR FERRITIC/MARTENSITIC STEEL HAVING IMPROVED CREEP RESISTANCE AND PREPARATION METHOD THEREOF 审中-公开
标题翻译：具有改进的抗蠕变性的高CR粉末/马氏体钢及其制备方法
公开(公告)号：US20110162764A1
公开(公告)日：2011-07-07
申请号：US12984811
申请日：2011-01-05
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： C21D8/02 , C21D6/00 , C22C38/00 , C22C38/54 , C22C38/46 , C22C38/44 , C22C38/48
CPC分类号： C21D6/002 , C21D1/28 , C21D7/13 , C21D8/0221 , C21D2211/005 , C21D2211/008 , C22C1/02 , C22C38/001 , C22C38/02 , C22C38/04 , C22C38/44 , C22C38/46 , C22C38/48 , C22C38/54
摘要： High-Cr ferritic/martensitic steels having an improved tensile strength and creep resistance are provided, which includes 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron, and optionally, 0.002˜0.010 weight % of phosphorus or 0.01˜0.08 weight % of zirconium, and iron balance. By regulating the contents of alloying elements such as niobium, tantalum, tungsten, nitrogen, boron, zirconium, carbon, the high-Cr ferritic/martensitic steels with superior tensile strength and creep resistance are provided, and can be effectively used as an in-core structural material for Generation IV sodium-cooled fast reactor (SFR) which is used under high temperature and high irradiation conditions.
摘要翻译：提供了具有改进的抗拉强度和抗蠕变性的高Cr铁素体/马氏体钢，其包括0.04〜0.13重量％的碳，0.03〜0.07重量％的硅，0.40〜0.50重量％的锰，0.40〜0.50重量％的镍，8.5〜9.5重量％的铬，0.45〜0.55重量％的钼，0.10〜0.25重量％的钒，0.02〜0.10重量％的钽，0.15〜0.25重量％的铌，1.5〜3.0重量％的钨， 0.05〜0.12重量％的氮，0.004〜0.008重量％的硼，以及任选的0.002〜0.10重量％的磷或0.01〜0.08重量％的锆和铁的平衡。通过调节铌，钽，钨，氮，硼，锆，碳等合金元素的含量，提供了具有优异的抗拉强度和抗蠕变性的高Cr铁素体/马氏体钢，在高温高照射条件下使用的第IV代钠冷快堆（SFR）的核心结构材料。

3. 发明授权

US09598750B2 High Cr ferritic/martensitic steels having an improved creep resistance for in-core component materials in nuclear reactor, and preparation method thereof 有权
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).

4. 发明申请

US20080192880A1 High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof 有权
标题翻译：高Fe含有具有优异耐腐蚀性的锆合金组合物及其制备方法
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。

5. 发明授权

US08070892B2 High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof 有权
标题翻译：高Fe含有具有优异耐腐蚀性的锆合金组合物及其制备方法
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。

6. 发明申请

US20080131306A1 ZIRCONIUM ALLOY COMPOSITION HAVING EXCELLENT CORROSION RESISTANCE FOR NUCLEAR APPLICATIONS AND METHOD OF PREPARING THE SAME 审中-公开
标题翻译：用于核应用的具有优异耐腐蚀性的锆合金组合物及其制备方法
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。

7. 发明授权

US06902634B2 Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding 有权
标题翻译：制造用于核燃料棒包层的含有铌的锆基合金的方法
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。

8. 发明授权

US5985211A Composition of zirconium alloy having low corrosion rate and high strength 失效
标题翻译：腐蚀速率低，强度高的锆合金组成
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。

9. 发明授权

US06811746B2 Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube 有权
标题翻译：锆合金具有优异的耐燃性和核燃料包层管的机械性能
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。

10. 发明授权

US06514360B2 Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel 有权
标题翻译：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
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。

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