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1.发明公开
公开(公告)号：EP0155168A2
公开(公告)日：1985-09-18
申请号：EP85301662.4
申请日：1985-03-11
CPC分类号： C22F1/186 , B32B15/01 , G21C3/20 , G21Y2002/103 , G21Y2002/104 , G21Y2002/303 , G21Y2004/10 , Y02E30/40
摘要： 5 Composite nuclear fuel rod cladding tubes including two concentric layers of zirconium base alloys metallurgically bonded to each other. The outer layer is composed of a conventional zirconium base alloy having high strength and excellent aqueous corrosion resistance. The inner layer is composed of a second zirconium base alloy containing from 0.2 to 0.6 wt.% tin, from 0.03 to 0.11 wt.% iron and up to 350 ppm oxygen. This second alloy while also having excellent aqueous corrosion resistance, is further characterized by the ability to prevent the propagation of cracks initiated during reactor operation due to pellet-cladding interaction.
摘要翻译： 复合核燃料棒包覆管包括两个同心层的锆基合金，它们彼此冶金地结合。 外层由具有高强度和优异的耐水腐蚀性的常规锆基合金组成。 内层由含有0.2-0.6重量％锡，0.03-0.11重量％铁和至多350ppm氧的第二锆基合金组成。 该第二种合金虽然具有优异的耐水腐蚀性，但其特征还在于能防止由于颗粒 - 包层相互作用而在反应器操作过程中引起的裂纹扩展。
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公开(公告)号：EP0415134B1
公开(公告)日：1994-06-22
申请号：EP90115098.7
申请日：1990-08-06
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21Y2002/103 , G21Y2004/10 , G21Y2004/20 , Y02E30/40
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3.发明公开
公开(公告)号：EP0317769A3
公开(公告)日：1990-10-31
申请号：EP88117552.5
申请日：1988-10-21
CPC分类号： G21C3/07 , C22C16/00 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/40 , Y02E30/40
摘要： Process for making zirconium alloys for use in liners of fuel element claddings. Electron beam melting of zirconium is utilized to give very low metallic impurities to reduce solid solution strengthening and second phase formation and property variability from lot to lot, while using alloying to reduce the susceptibility to steam corrosion. Preferably, oxygen is controlled to a low level as well, to provide a low, but fabricable, hardness in the alloyed liner material.
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4.发明公开Water reactor fuel element cladding tube 无效Hüllröhrefüreinen Brennstab eineswassergekühltenReaktors。
公开(公告)号：EP0194797A1
公开(公告)日：1986-09-17
申请号：EP86301529.3
申请日：1986-03-04
发明人： Foster, John Paul
CPC分类号： G21C3/07 , B32B15/01 , G21Y2002/103 , G21Y2004/10 , Y02E30/40
摘要： 57 A water reactor fuel cladding tube is provided with two zirconium base alloy concentric layers. The outer layer is composed of a high strength zirconium base alloy having excellent aqueous corrosion resistance. Metallurgically bonded to the outer layer is an inner layer composed of a zirconium base alloy consisting essentially of from 0.4 to 0.6 wt.% tin; from 0.5 to 1.4 wt.% iron; and from 100 to 700 ppm oxygen.
摘要翻译： 水反应堆燃料包层管设有两个锆基合金同心层。 外层由耐水腐蚀性优异的高强度锆基合金构成。 与外层金属结合的是由基本上由0.4至0.6重量％锡组成的锆基合金构成的内层; 0.5至1.4重量％的铁; 和100至700ppm的氧气。
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5.发明授权
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6.发明公开Zirlo material composition and fabrication processing 失效Zirlo-Werkstoffzusammensetzung und Herstellungsverfahren。
公开(公告)号：EP0475159A1
公开(公告)日：1992-03-18
申请号：EP91114158.8
申请日：1991-08-23
CPC分类号： G21C3/06 , C22F1/186 , G21Y2002/10 , G21Y2004/20 , Y02E30/40
摘要： This invention is for the processing of a somewhat broader range of compositions, including ZIRLO material. It controls creep rate in an alloy having, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.28 of at least one of iron, nickel and chromium and up to 220 ppm carbon, and the balance essentially zirconium. The method is of a type which utilizes subjecting the material to a post extrusion anneal, a series of intermediate area reductions and intermediate recrystallization anneals, with one of the intermediate recrystallization anneals possibly being a late stage beta-quench, a final pass area reduction, and a final stress relief anneal. The creep rate is controlled to about the desired amount per hour by the use of an average intermediate recrystallization annealing temperature and a final pass area reduction combination selected from the designated area of a designated figure, with the figure being selected based on whether the post extrusion anneal was an alpha or a beta anneal; on whether the final anneal was a stress relief anneal or a recrystallization anneal, and whether or not a late stage beta-quench was utilized, and the desired creep rate range. The method may also comprise subjecting the material to an alpha post extrusion anneal and a final stress relief anneal, and controlling the creep rate by the use of certain intermediate recrystallisation annealing temperatures and final pass true area reductions.
摘要翻译： 本发明用于处理包括ZIRLO材料在内的稍宽范围的组合物。 它控制合金中的蠕变速率，其重量百分数为0.5-2.0铌，0.7-1.5锡，0.07-0.28的铁，镍和铬中的至少一种和至多220ppm的碳，余量基本上是锆。 该方法是使用材料进行后挤压退火，一系列中间区域减少和中间再结晶退火的类型，其中一个中间再结晶退火可能是晚期β-淬火，最终通过面积减小， 和最终的应力消除退火。 通过使用选自指定图的指定区域的平均中间再结晶退火温度和最终通过面积减少组合，将蠕变速率控制在大约每小时所需的量，该图根据后挤压 退火是α或β退火; 关于最终退火是否是应力消除退火还是再结晶退火，以及是否使用后期β-淬火以及期望的蠕变速率范围。 该方法还可以包括对材料进行α后挤出退火和最终的应力消除退火，并且通过使用某些中间再结晶退火温度和最终通过真实面积减少来控制蠕变速率。
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7.发明公开Zirconium based alloy material for light water reactor applications 无效Legierungswerkstoff auf Zirkoniumbasis zur Anwendung bei einem Leichtwasserreaktor。
公开(公告)号：EP0415134A1
公开(公告)日：1991-03-06
申请号：EP90115098.7
申请日：1990-08-06
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21Y2002/103 , G21Y2004/10 , G21Y2004/20 , Y02E30/40
摘要： This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200-1300°F, and to a beta quench two steps prior to final size.
摘要翻译： 这是一种合金，其包括按重量百分比计的0.5-2.0铌，0.7-1.5锡，0.07-0.14铁和0.03-0.14的镍和铬中的至少一种，以及至少0.12总铁，镍和铬， 和高达220ppm C，余量基本上是锆。 优选地，合金含有0.03-0.08铬和0.03-0.08镍。 合金还优选在约1200-1300°F的温度下进行中间再结晶退火，并在最终尺寸之前进行两步骤的β淬火。
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公开(公告)号：EP0155168A3
公开(公告)日：1986-10-01
申请号：EP85301662
申请日：1985-03-11
CPC分类号： C22F1/186 , B32B15/01 , G21C3/20 , G21Y2002/103 , G21Y2002/104 , G21Y2002/303 , G21Y2004/10 , Y02E30/40
摘要： 5 Composite nuclear fuel rod cladding tubes including two concentric layers of zirconium base alloys metallurgically bonded to each other. The outer layer is composed of a conventional zirconium base alloy having high strength and excellent aqueous corrosion resistance. The inner layer is composed of a second zirconium base alloy containing from 0.2 to 0.6 wt.% tin, from 0.03 to 0.11 wt.% iron and up to 350 ppm oxygen. This second alloy while also having excellent aqueous corrosion resistance, is further characterized by the ability to prevent the propagation of cracks initiated during reactor operation due to pellet-cladding interaction.
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公开(公告)号：EP0475159B1
公开(公告)日：1996-10-16
申请号：EP91114158.8
申请日：1991-08-23
CPC分类号： G21C3/06 , C22F1/186 , G21Y2002/10 , G21Y2004/20 , Y02E30/40
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公开(公告)号：EP0559096A1
公开(公告)日：1993-09-08
申请号：EP93103086.0
申请日：1993-02-26
CPC分类号： C22F1/186
摘要： A Zirlo alloy formed by beta quenching, hot deforming, recrystallize annealing and then cold deforming said alloy a plurality of times with recrystallize anneal steps performed between the cold deforming steps followed by stress relief annealing. The fabricating method can include a late stage beta quench step in place of one of the recrystallize anneal steps. The recrystallization anneals take place at 649 to 760°C.
摘要翻译： 通过β淬火，热变形，再结晶退火形成的Zirlo合金，然后在冷变形步骤之后执行应力消除退火，在所述合金多次冷再变形，再结晶退火步骤。 制造方法可以包括后期阶段β淬火步骤代替一个再结晶退火步骤。 再结晶退火发生在649〜760℃
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