公开(公告)号：US09139895B2

公开(公告)日：2015-09-22

申请号：US10935157

申请日：2004-09-08

申请人： David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

发明人： David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

IPC分类号： C22F1/18 ,  C22C16/00

CPC分类号： C22F1/186 ,  C22C16/00

摘要： Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about 0.31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.

摘要翻译： 本文公开了锆基合金和从这种在侵蚀性冷却剂组合物中表现出改进的耐腐蚀性的合金制造核反应堆部件，特别是燃料包壳管的方法。 制造步骤包括在管的外部区域的后期和后处理。 锆基合金将包括约1.30至1.60重量％的锡; 约0.06至0.15重量％的铬; 约0.16至0.24重量％的铁，以及0.05至0.08重量％的镍，其中铁，铬和镍的总含量高于合金的约0.31重量％，其特征在于具有平均尺寸的第二相沉淀 通常小于约40nm。 最终完成的包层将具有小于约0.50μmRa的表面粗糙度，优选小于约0.10μmRa的表面粗糙度。

公开(公告)号：US20060048869A1

公开(公告)日：2006-03-09

申请号：US10935156

申请日：2004-09-08

申请人： David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts ,  Robert Elkins ,  Hiroaki Kagami ,  Hideyuki Mukai

发明人： David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts ,  Robert Elkins ,  Hiroaki Kagami ,  Hideyuki Mukai

IPC分类号： C22F1/18

CPC分类号： C22F1/186 ,  C22C16/00 ,  G21C3/07 ,  G21C21/00 ,  Y02E30/40

摘要： Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibt a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

摘要翻译： 本文公开的是锆基合金，其可以被制造成形成核反应堆组分，特别是燃料包覆管，其表现出足够的耐腐蚀性和吸氢特性，而不需要晚期α+β或β-猝灭过程。 锆基合金将包括约1.30-1.60重量％的锡; 0.0975-0.15重量％铬; 0.16-0.24重量％铁; 和至多约0.08重量％的镍，其中铁，铬和镍的总含量占合金的至少约0.3175重量％。 所得到的组分将显示平均沉淀尺寸为约50至100nm的表面区域和小于约2×10 -19小时的Sigma A，其中工件加工通常限于低于680℃的温度 ℃，对于所有其他操作，低于625℃，从而简化核反应堆组件的制造，同时提供与常规合金相当的耐腐蚀性。

公开(公告)号：US08116422B2

公开(公告)日：2012-02-14

申请号：US11320477

申请日：2005-12-29

申请人： Daniel Reese Lutz ,  Gerald Allen Potts ,  Yang-Pi Lin ,  Sheikh Tahir Mahmood ,  Mark Andrew Dubecky ,  David William White ,  John Schardt

发明人： Daniel Reese Lutz ,  Gerald Allen Potts ,  Yang-Pi Lin ,  Sheikh Tahir Mahmood ,  Mark Andrew Dubecky ,  David William White ,  John Schardt

IPC分类号： G21C9/00 ,  G21C7/10

CPC分类号： G21C3/07 ,  G21C3/324 ,  G21Y2002/203 ,  G21Y2002/207 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

摘要： A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.

摘要翻译： 适用于形成反应器组分的锆合金，其在轻水反应器（LWR），例如沸水反应器（BWR）的操作期间表现出减少的照射生长和改善的耐腐蚀性。 在反应器的操作期间，反应器部件将暴露于足以引起或加速反应堆堆芯内辐射的合金表面的腐蚀的强烈且常常不对称的辐射场。 由公开的锆合金制造的反应器部件也将倾向于在部件制造期间显示出对冷加工的改善的公差，从而通过减少或消除随后的热处理（例如退火）来简化这些部件的制造，而不会不适当地降低 成品组件的性能。

公开(公告)号：US20060048870A1

公开(公告)日：2006-03-09

申请号：US10935157

申请日：2004-09-08

申请人： David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

发明人： David White ,  Daniel Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts

IPC分类号： C22F1/18

CPC分类号： C22F1/186 ,  C22C16/00

摘要： Disclosed herein are zirconium-based alloys and methods of fabricating nuclear reactor components, particularly fuel cladding tubes, from such alloys that exhibit improved corrosion resistance in aggressive coolant compositions. The fabrication steps include a late-stage β-treatment on the outer region of the tubes. The zirconium-based alloys will include between about 1.30 and 1.60 wt % tin; between about 0.06 and 0.15 wt % chromium; between about 0.16 and 0.24 wt % iron, and between 0.05 and 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising above about .31 wt % of the alloy and will be characterized by second phase precipitates having an average size typically less than about 40 nm. The final finished cladding will have a surface roughness of less than about 0.50 μm Ra and preferably less then about 0.10 μm Ra.

摘要翻译： 本文公开了锆基合金和从这种在侵蚀性冷却剂组合物中表现出改进的耐腐蚀性的合金制造核反应堆部件，特别是燃料包壳管的方法。 制造步骤包括在管的外部区域的后期β-治疗。 锆基合金将包括约1.30至1.60重量％的锡; 约0.06至0.15重量％的铬; 约0.16至0.24重量％的铁和0.05至0.08重量％的镍，其中铁，铬和镍的总含量高于合金的约31.重量％，并且其特征在于具有平均值的第二相沉淀物 尺寸通常小于约40nm。 最终完成的包层将具有小于约0.50μmRa的表面粗糙度，优选小于约0.10μmRa。

公开(公告)号：US1555881A

公开(公告)日：1925-10-06

申请号：US2929625

申请日：1925-05-11

申请人： JOHN SCHARDT

发明人： JOHN SCHARDT

IPC分类号： A01B15/18

CPC分类号： A01B15/18

公开(公告)号：US20070153963A1

公开(公告)日：2007-07-05

申请号：US11320477

申请日：2005-12-29

申请人： Daniel Lutz ,  Gerald Potts ,  Yang-Pi Lin ,  Sheikh Mahmood ,  Mark Dubecky ,  David White ,  John Schardt

发明人： Daniel Lutz ,  Gerald Potts ,  Yang-Pi Lin ,  Sheikh Mahmood ,  Mark Dubecky ,  David White ,  John Schardt

IPC分类号： G21C1/04

CPC分类号： G21C3/07 ,  G21C3/324 ,  G21Y2002/203 ,  G21Y2002/207 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

摘要： A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.

摘要翻译： 适用于形成反应器组分的锆合金，其在轻水反应器（LWR），例如沸水反应器（BWR）的操作期间表现出减少的照射生长和改善的耐腐蚀性。 在反应器的操作期间，反应器部件将暴露于足以引起或加速反应堆堆芯内辐射的合金表面的腐蚀的强烈且常常不对称的辐射场。 由公开的锆合金制造的反应器部件也将倾向于在部件制造期间显示出对冷加工的改善的公差，从而通过减少或消除随后的热处理（例如退火）来简化这些部件的制造，而不会不适当地降低 成品组件的性能。

公开(公告)号：US08043448B2

公开(公告)日：2011-10-25

申请号：US10935156

申请日：2004-09-08

申请人： David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts ,  Robert Elkins ,  Hiroaki Kagami ,  Hideyuki Mukai

发明人： David White ,  Daniel R. Lutz ,  Yang-Pi Lin ,  John Schardt ,  Gerald Potts ,  Robert Elkins ,  Hiroaki Kagami ,  Hideyuki Mukai

IPC分类号： C22F1/18

CPC分类号： C22F1/186 ,  C22C16/00 ,  G21C3/07 ,  G21C21/00 ,  Y02E30/40

摘要： Disclosed herein are zirconium-based alloys that may be fabricated to form nuclear reactor components, particularly fuel cladding tubes, that exhibit sufficient corrosion resistance and hydrogen absorption characteristics, without requiring a late stage α+β or β-quenching processes. The zirconium-base alloys will include between about 1.30-1.60 wt % tin; 0.0975-0.15 wt % chromium; 0.16-0.24 wt % iron; and up to about 0.08 wt % nickel, with the total content of the iron, chromium and nickel comprising at least about 0.3175 wt % of the alloy. The resulting components will exhibit a surface region having a mean precipitate sizing of between about 50 and 100 nm and a Sigma A of less than about 2×10−19 hour with the workpiece processing generally being limited to temperatures below 680° C. for extrusion and below 625° C. for all other operations, thereby simplifying the fabrication of the nuclear reactor components while providing corrosion resistance comparable with conventional alloys.

摘要翻译： 这里公开的是锆基合金，其可以被制造成形成核反应堆组分，特别是燃料包覆管，其表现出足够的耐腐蚀性和氢吸收特性，而不需要晚期α+和bgr; 或＆bgr; - 修复过程。 锆基合金将包括约1.30-1.60重量％的锡; 0.0975-0.15重量％铬; 0.16-0.24重量％铁; 和至多约0.08重量％的镍，其中铁，铬和镍的总含量占合金的至少约0.3175重量％。 所得组分将表现出具有约50-100nm的平均沉淀尺寸的表面区域和小于约2×10-19小时的Sigma A，其中工件加工通常限于低于680℃的温度用于挤出 并且对于所有其他操作而言低于625℃，从而简化了核反应堆部件的制造，同时提供了与常规合金相当的耐腐蚀性。