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。

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。