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2.发明授权PROCEDE DE FABRICATION D'UN TUBE DE GAINAGE DE COMBUSTIBLE POUR REACTEUR NUCLEAIRE, ET TUBE AINSI OBTENU 有权用于生产燃料外套管用于核反应堆及其制品PIPE
公开(公告)号：EP1781833B1
公开(公告)日：2008-01-30
申请号：EP05790867.5
申请日：2005-07-19
申请人： Areva NP
CPC分类号： C22C16/00 , G21C3/07 , G21C21/00 , G21Y2002/103 , G21Y2004/10 , G21Y2004/20 , G21Y2004/40 , Y02E30/40
摘要： The invention relates to a method for production of a fuel casing 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 = 100ppm, 600ppm = O = 2300ppm, 5ppm = S = 100ppm, Cr + V = 0,25 %, Hf = 75ppm, F = 1ppm 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 annealing s being carried out at a temperature below the a ? a + ß 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?m. The invention further relates to a fuel cladding tube obtained thus.
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3.发明公开
公开(公告)号：EP2126926A1
公开(公告)日：2009-12-02
申请号：EP07871813.7
申请日：2007-12-07
申请人： Areva NP
CPC分类号： C22C16/00 , G21C3/07 , G21C3/60 , G21Y2002/103 , G21Y2004/40 , Y02E30/38
摘要： The invention relates to a method for design of a fuel assembly for nuclear reactors, comprising structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which said components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between -10 et -20 MPa are made from an alloy with a content of Sn between Sn = (-0.025σ - 0.25) % and Sn = -0.05σ % : those components subjected to such a stress of between 0 et -10 MPa are made from an alloy the Sn content of which is between Sn = traces and Sn = (0.05σ + 1) %: those components subjected to such a stress of between 0 and +10MPa are made from an alloy the Sn content of which is between Sn = 0.05σ % and Sn = (0.07σ + 1) %:and those components subjected to such a stress of between +10 and +20MPa are made from an alloy the content of SN of which is between 0.50 % and 1.70%. Fuel assembly made according to said method.
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4.发明公开PROCEDE DE FABRICATION D'UN TUBE DE GAINAGE DE COMBUSTIBLE POUR REACTEUR NUCLEAIRE, ET TUBE AINSI OBTENU 有权用于生产燃料外套管用于核反应堆及其制品PIPE
公开(公告)号：EP1781833A1
公开(公告)日：2007-05-09
申请号：EP05790867.5
申请日：2005-07-19
申请人： Areva NP
CPC分类号： C22C16/00 , G21C3/07 , G21C21/00 , G21Y2002/103 , G21Y2004/10 , G21Y2004/20 , G21Y2004/40 , Y02E30/40
摘要： The invention relates to a method for production of a fuel casing 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 = 100ppm, 600ppm = O = 2300ppm, 5ppm = S = 100ppm, Cr + V = 0,25 %, Hf = 75ppm, F = 1ppm 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 annealing s being carried out at a temperature below the a ? a + ß 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 0,5µm. The invention further relates to a fuel cladding tube obtained thus.
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5.发明授权ALLIAGE DE ZIRCONIUM RESISTANT A LA CORROSION EN OMBRES PORTEES POUR COMPOSANT D'ASSEMBLAGE DE COMBUSTIBLE POUR REACTEUR A EAU BOUILLANTE, COMPOSANT REALISE EN CET ALLIAGE, ASSEMBLAGE DE COMBUSTIBLE ET SON UTILISATION 有权ALLIAGE DE ZIRCONIUM耐腐蚀性A腐蚀性EN OMBRES PORTEES POUR COMPOSANT D ASSEMBLAGE DE可燃性废气A EAU BOUILLANTE，合成气实现EN CET ALLIAGE，装配可燃性ET SON利用
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6.发明授权
公开(公告)号：EP2126926B1
公开(公告)日：2014-11-05
申请号：EP07871813.7
申请日：2007-12-07
申请人： Areva NP
CPC分类号： C22C16/00 , G21C3/07 , G21C3/60 , G21Y2002/103 , G21Y2004/40 , Y02E30/38
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7.发明公开
公开(公告)号：EP2099943A1
公开(公告)日：2009-09-16
申请号：EP07870314.7
申请日：2007-11-21
申请人： Areva NP
IPC分类号： C22C16/00
摘要： The invention relates to a zirconium alloy which is resistant to corrosion in drop shadows for a fuel assembly component for a boiling water nuclear reactor. Said alloy is characterised in that it is composed of, in weight percentages: ' Nb = 0,4 - 4,5% ' Sn = 0,20 - 1,7% ' Fe = 0,05 - 0,45% ' Fe + Cr + Ni + V = 0,05 - 0,45% avec Nb 9 x [0,5-(Fe+Cr+Ni+V)] ' S = traces - 400ppm ' C = traces - 200ppm ' Si = traces - 120ppm ' O = 600 - 1800ppm, the remainder being Zr and impurities resulting from the production method. The alloy according to the invention is also characterised in that, during the production, after its last hot deformation, it was subjected to at least one thermal treatment between 450 and 610°C for a total duration of at least 4 hours, and at least one cold-rolling process at a rolling rate of at least 25 %; and in that a final thermal treatment is carried out between 450°C and 610°C for between 1 minute and 20 hours. The invention also relates to a fuel assembly component produced using said alloy, a fuel assembly comprising said alloy, and the use of same.
摘要翻译： 锆合金耐阴影腐蚀，用于沸水核反应堆燃料组件部件包括其制造过程中铌，锡，铁，硫，碳，硅和氧的组合物，并且所述合金包含的制备，它的负荷热变形后 ，热处理在450〜610 [℃持续至少4小时，然后冷轧用的至少25％的轧制率和最终热处理在450〜610 [℃持续1-20小时。 锆合金耐腐蚀阴影，用于沸水核反应堆燃料组件构件包括组合物（以wt。％）铌（0.4-4.5），锡（0.2-1.7），铁（0:05至0:45），铁的总和中， 铬，镍和钒（0:05至0:45），硫（迹线为400ppm），碳（迹线200 ppm的），硅（迹线至120ppm的）和氧（600-1800 ppm的），其余为锆和其他 杂质从所得的发展，提供没有铌存在于9X [0.5-（铁+铬镍+钒+）]，和所述合金包含的制备中，它的制造过程中，它的负荷热变形，在450-热处理后 610 [℃持续至少4小时，然后冷轧用的至少25％的轧制率和最终热处理在450〜610 [℃持续1-20小时。 独立权利要求中包括了：（1）沸水核反应堆燃料组件部件，由所述合金制成; 和（2）沸水核反应堆燃料组件，包括由至少一些组件易受合金的沸水核反应堆燃料组件部件基于镍或不锈钢与其它合金成分电耦合状态被放置 ， 锆合金是在燃料组分中是有用的的沸水核反应堆初级流体含有最多至400份每溶解氧的兆，高达50毫升/公斤的溶解氢，每锌的兆，因此至多50份 包含加入到减少在与反应器接触的材料的腐蚀电位的化学物质。
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