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    Method of manufacturing a fuel cladding tube for a nuclear reactor, and a tube obtained thereby
    1.
    发明授权
    Method of manufacturing a fuel cladding tube for a nuclear reactor, and a tube obtained thereby 有权
    制造核反应堆用燃料包层管的方法及由此得到的管

    公开(公告)号：US07738620B2

    公开(公告)日：2010-06-15

    申请号：US11659656

    申请日：2005-07-19

    申请人： Pierre Barberis ,  Jean-Paul Mardon ,  Véronique Rebeyrolle ,  Jean-Luc Aubin

    发明人： Pierre Barberis ,  Jean-Paul Mardon ,  Véronique Rebeyrolle ,  Jean-Luc Aubin

    IPC分类号： G21C3/00

    CPC分类号： C22C16/00 ,  G21C3/07 ,  G21C21/00 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/40 ,  Y02E30/40

    摘要： A method for production of a fuel cladding tube for a nuclear reactor, characterized by the preparation of an ingot of an alloy of zirconium with the following composition by weight %: 0.8%≦Nb≦2.8%, traces≦Sn≦0.65%, 0.015%≦Fe≦0.40%, C≦100 ppm, 600 ppm≦O≦2300 ppm, 5 ppm≦S≦100 ppm, Cr+V≦0.25%, Hf≦75 ppm and F≦1 ppm the remainder being zirconium and impurities arising from production. The ingot is then subjected to forging, a hardening and thermomoechanical treatments comprising cold laminations separated by intermediate annealing, all intermediate annealings being carried out at a temperature below the α→α+β transition temperature of the alloy, finishing with a recrystallization annealing and resulting in the production of a tube, whereupon an optional external cleaning of the tube is carried out and a mechanical polishing of the external surface of the tube is carried out to give a roughness Ra less than or equal to 0.5 μm. The invention further relates to a fuel cladding tube obtained thereby.

    摘要翻译： 一种生产用于核反应堆的燃料包层管的方法，其特征在于制备具有以下组成的锆的合金锭：0.8％＆lt; NlE; Nb＆nlE; 2.8％，痕量Sn; nnE; 0.65％ 0.015％＆nlE; Fe＆nlE; 0.40％，C＆lt; lE; 100ppm，600ppm＆amp; NlE; O＆amp; NEE; 2300ppm，5ppm和nlE; S＆amp; NlE; 100ppm，Cr + V和NlE; 0.25％，Hf和nEE; 75ppm和F＆ 和生产中产生的杂质。 然后对锭进行锻造，硬化和热机械处理，包括通过中间退火分离的冷层压，所有中间退火在低于α→α+和bgr的温度下进行; 合金的转变温度，用再结晶退火进行精加工，从而制造管，由此执行管的可选的外部清洁，并且进行管的外表面的机械抛光以得到粗糙度Ra 小于或等于0.5μm。 本发明还涉及由此获得的燃料包壳管。

    Method Of Manufacturing A Fuel Cladding Tube For A Nuclear Reactor, And A Tube Obtained Thereby
    2.
    发明申请
    Method Of Manufacturing A Fuel Cladding Tube For A Nuclear Reactor, And A Tube Obtained Thereby 有权
    制造用于核反应堆的燃料包覆管和由此获得的管的方法

    公开(公告)号：US20080080660A1

    公开(公告)日：2008-04-03

    申请号：US11659656

    申请日：2005-07-19

    申请人： Pierre Barberis ,  Jean-Paul Mardon ,  Veronique Rebeyrolle ,  Jean-Luc Aubin

    发明人： Pierre Barberis ,  Jean-Paul Mardon ,  Veronique Rebeyrolle ,  Jean-Luc Aubin

    IPC分类号： G21C3/07

    CPC分类号： C22C16/00 ,  G21C3/07 ,  G21C21/00 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/40 ,  Y02E30/40

    摘要： A method for production of a fuel cladding tube for a nuclear reactor, characterised by the preparation of an ingot of an alloy of zirconium with the following composition by weight %: 0.8%≦Nb≦2.8%, traces≦Sn≦0.65%, 0.015%≦Fe≦0.40%, C≦100 ppm, 600 ppm≦O≦2300 ppm, 5 ppm≦S≦100 ppm, Cr+V≦0.25%, Hf≦75 ppm and F≦1 ppm the remainder being zirconium and impurities arising from production. The ingot is then subjected to forging, a hardening and thermomoechanical treatments comprising cold laminations separated by intermediate annealing, all intermediate annealings being carried out at a temperature below the α→α+β transition temperature of the alloy, finishing with a recrystallisation annealing and resulting in the production of a tube, whereupon an optional external cleaning of the tube is carried out and a mechanical polishing of the external surface of the tube is carried out to give a roughness Ra less than or equal to 0.5 μm. The invention further relates to a fuel cladding tube obtained thereby.

    摘要翻译： 一种核反应堆用燃料包层管的制造方法，其特征在于，以下述组成按重量％的比例制备锆合金锭：0.8％<= Nb <= 2.8％，痕量<= Sn <= 0.65％，0.015％<= Fe <= 0.40％，C <= 100ppm，600ppm <= O <= 2300ppm，5ppm <= S <= 100ppm，Cr + V <= 0.25％ 75ppm，F <= 1ppm，其余为锆和生产产生的杂质。 然后对铸锭进行锻造，包括通过中间退火分离的冷层压的硬化和热机械处理，所有中间退火在低于合金的α→α+β转变温度的温度下进行，用再结晶退火完成， 导致管的制造，由此执行管的可选的外部清洁，并且执行管的外表面的机械抛光以获得小于或等于0.5μm的粗糙度Ra。 本发明还涉及由此获得的燃料包壳管。

    Tube for a nuclear fuel assembly, and method for making same
    3.
    再颁专利
    Tube for a nuclear fuel assembly, and method for making same 失效
    用于核燃料组件的管及其制造方法

    公开(公告)号：USRE43182E1

    公开(公告)日：2012-02-14

    申请号：US10624757

    申请日：1996-07-22

    申请人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

    发明人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

    IPC分类号： G21C3/06

    CPC分类号： G21C3/07 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/302 ,  G21Y2004/10 ,  G21Y2004/40 ,  Y02E30/40

    摘要： A zirconium alloy tube for forming the whole or the outer portion of a nuclear fuel pencil housing or a nuclear fuel assembly guide tube. The zirconium alloy contains 0.8-1.8 wt. % of niobium, 0.2-0.6 wt. % of tin and 0.02-0.4 wt. % of iron, and has a carbon content of 30-180 ppm, a silicon content of 10-120 ppm and an oxygen content of 600-1800 ppm. The tube may be used when recrystallized or stress relieved.

    摘要翻译： 一种用于形成核燃料铅笔盒或核燃料组件引导管的整体或外部的锆合金管。 锆合金含有0.8-1.8wt。 ％的铌，0.2-0.6wt。 锡和0.02-0.4重量％ 的铁，并且具有30-180ppm的碳含量，10-120ppm的硅含量和600-1800ppm的氧含量。 当重结晶或减轻应力时，可以使用该管。

    Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same
    4.
    发明授权
    Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same 失效
    用于核反应堆燃料组件的锆合金管及其制造方法

    公开(公告)号：US5887045A

    公开(公告)日：1999-03-23

    申请号：US875481

    申请日：1997-07-29

    申请人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

    发明人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

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

    CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

    摘要： A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.

    摘要翻译： PCT No.PCT / FR96 / 00137 Sec。 371日期1997年7月29日第 102（e）日期1997年7月29日PCT 1996年1月26日PCT PCT。 公开号WO96 / 24140 日期1996年8月8日一种用于构成用于核燃料组件的包层或导管的全部或一部分的锆基合金管。 该管由合金含有1.0-1.7％的锡，0.55-0.80％的铁，0.20-0.60％的铬和/或钒和0.10-0.18％的氧，其中50-200 碳的碳和50-120ppm的硅。 该合金还含有锆和不可避免的杂质，并且完全重结晶。

    Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby
    5.
    发明授权
    Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby 失效
    制造核燃料组件用管的方法，以及由此获得的管

    公开(公告)号：US5648995A

    公开(公告)日：1997-07-15

    申请号：US579372

    申请日：1995-12-27

    申请人： Jean-Paul Mardon ,  Jean Sevenat ,  Daniel Charquet

    发明人： Jean-Paul Mardon ,  Jean Sevenat ,  Daniel Charquet

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

    CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/40 ,  Y02E30/40

    摘要： The method serves to manufacture tubes for constituting sheaths for nuclear fuel rods. A bar is made out of a zirconium-based alloy containing 50 ppm to 250 ppm iron, 0.8% to 1.3% by weight niobium, less than 1600 ppm oxygen, less than 200 ppm carbon, and less than 120 ppm silicon. The bar is heated to a temperature in the range 1000.degree. C. to 1200.degree. C. and is quenched in water. A blank is extruded after heating to a temperature in the range 600.degree. C. to 800.degree. C. and cold-rolled in at least four passes in order to obtain a tube, with intermediate heat treatment being performed between passes at temperatures in the range 560.degree. C. to 620.degree. C. A final heat treatment is performed at a temperature in the range 560.degree. C. to 620.degree. C., all of the heat treatments being performed under an inert atmosphere or a vacuum.

    摘要翻译： 该方法用于制造用于构成核燃料棒的护套的管。 棒由含有50ppm至250ppm铁，0.8％至1.3％重量铌，小于1600ppm氧，小于200ppm碳和小于120ppm硅的锆基合金制成。 将该棒加热至1000℃至1200℃的温度，并在水中淬灭。 在加热到600℃至800℃的温度之后将坯料挤出，并在至少四道次中进行冷轧，以获得管，在通过之间进行中间热处理，其温度范围为 560℃至620℃。在560℃至620℃的温度下进行最终热处理，所有热处理均在惰性气氛或真空下进行。

    Sheathing tube for a nuclear fuel rod
    10.
    发明授权
    Sheathing tube for a nuclear fuel rod 失效
    用于核燃料棒的护套管

    公开(公告)号：US5735978A

    公开(公告)日：1998-04-07

    申请号：US730013

    申请日：1996-10-11

    申请人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

    发明人： Jean-Paul Mardon ,  Jean Senevat ,  Daniel Charquet

    IPC分类号： C22C16/00 ,  C22F1/00 ,  C22F1/18 ,  G21C3/06 ,  G21C3/07 ,  C22C1/18

    CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/20 ,  Y02E30/40

    摘要： A method of manufacturing a tube suitable for use as sheath of a nuclear fuel rod zirconium based alloy. The alloy contains 0.18% to 0.25% iron, 0.07% to 0.13% chromium, 0.35% to 1.70% tin, all percentages by weight, 900 ppm to 2300 ppm oxygen, 80 ppm to 200 ppm carbon, and 50 ppm to 120 ppm silicon. A drawn blank is subjected to successive passes of metallurgical treatment and of heat treatment. The Fe/Cr ratio by weight in the alloy lies in the range 1.6 to 3. The heat treatment includes, after at least one rolling pass, a plurality of annealing passes under an inert atmosphere such that the sum .SIGMA.A is greater than 1.5.10.sup.-17, and advantageously in the range 2.10.sup.-17 to 2.10.sup.-16. The first rolling pass is performed on the tube coming from the drawing operation, without an intermediate annealing. .SIGMA.A designates the sum of the products of the times t (in hours) multiplied by the exponential of --Q/RT, where T is the temperature in K.

    摘要翻译： 一种制造适用于核燃料棒锆基合金护套的管的方法。 该合金含有0.18％至0.25％的铁，0.07％至0.13％的铬，0.35％至1.70％的锡，所有重量百分比，900ppm至2300ppm的氧，80ppm至200ppm的碳和50ppm至120ppm的硅 。 拉制的坯料经过冶金处理和热处理的连续通过。 合金中的Fe / Cr重量比在1.6至3的范围内。热处理包括在至少一次轧制过程之后，在惰性气氛下进行多次退火，使得SIGMAA总和大于1.5。 10-17，有利地在2.10-17至2.10-16的范围内。 在来自拉制操作的管上执行第一轧制道次，而不进行中间退火。 SIGMA A表示时间乘积+ E，uns t + EE（以小时为单位）乘以-Q / RT的指数的乘积之和，其中T是以K为单位的温度。