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    Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel
    2.
    发明公开
    Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel 有权
    一种用于制造用于具有高燃耗核燃料由铌entaltenden锆合金的片材或管过程

    公开(公告)号：EP1225243A1

    公开(公告)日：2002-07-24

    申请号：EP01201703.4

    申请日：2001-05-09

    申请人： Korea Atomic Energy Research Institute ,  Korea Electric Power Corporation

    发明人： Jeong, Yong Hwan ,  Baek, Jong Hyuk ,  Choi, Byoung Kwon ,  Kim, Kyeong Ho ,  Lee, Myong Ho ,  Park, Sang Yoon ,  Nam, Cheol ,  Jung, Younho

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

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

    摘要： Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at β phase range; β-quenching the forged ingot after solution heat-treatment at 1015-1075 °C; hot-working the quenched ingot at 600-650 °C; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600 °C, wherein temperatures of intermediate vacuum annealing and final vacuum annealing after β-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (Σ A) is limited to 1.0 × 10 -18 hr or lower, thereby yielding a tube and a sheet of Nb-containing zirconium alloys with excellent corrosion resistance and mechanical properties, capable of stably maintaining nuclear fuel in operation conditions of high temperature/high pressure of high burn-up reactor cores. Such Nb-added zirconium alloys are useful as nuclear fuel cladding tubes, grids and structures of the cores in the light water reactors and heavy water reactors.

    摘要翻译： 本发明公开了一种用于制造管和含铌的锆合金为高燃耗核燃料的片材的方法。 该方法包括：熔化添加Nb的锆合金，以锭; 锻造在β相范围的锭; 测试-quenching固溶热处理后的锻造锭在一○一五年至1075年℃; 热加工在600-650℃下骤冷的锭; 冷加工在三到五关热加工锭，与中间真空退火; 和最终真空退火在440-600℃下的冷加工锭，β--quenching后中间真空退火和最终真空退火的温度worin被改变，以便获得在其下沉淀在合金基体中被限制为平均的条件 为80nm或更小的和累积的退火参数（SIGMA A）直径被限制为1.0×10 <-18> hr以下，由此产生的管和具有优良的耐蚀性和机械性能含Nb锆合金的片材， 能够在高温/高燃耗反应堆堆芯的高压的运行条件稳定地保持核燃料。 添加Nb的搜索锆合金作为核燃料包壳管，格栅，并在轻水反应堆和重水反应堆芯的结构是有用的。

    Zirconium alloy having excellent corrosion resistance and mechanical properties and method for preparing nuclear fuel cladding tube by zirconium alloy
    4.
    发明公开
    Zirconium alloy having excellent corrosion resistance and mechanical properties and method for preparing nuclear fuel cladding tube by zirconium alloy 有权
    与锆合金包壳管的改进的耐腐蚀性和改进的机械性能和生产方法，用于核反应堆燃料棒锆合金

    公开(公告)号：EP1256634A1

    公开(公告)日：2002-11-13

    申请号：EP01309314.1

    申请日：2001-11-02

    申请人： Korea Atomic Energy Research Institute ,  Korea Hydro & Nuclear Power Co., Ltd.

    发明人： Jeong, Yong Hwan ,  Baek, Jong Hyuk ,  Choi, Byoung Kwon ,  Park, Sang Yoon ,  Nam, Cheol ,  Jung, Youn Ho ,  Lee, Myung Ho

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

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

    摘要： The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a=0.05-0.4 wt%, b=0.3-0.7 wt%, c=0.1-0.4 wt%, d=0-0.2 wt% and e=0.01-0.2 wt%, provided that Nb+Sn=0.35-1.0 wt%), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at β phase range, β-quenching the forged ingot at 1015-1075 °c, hot-working the quenched ingot at 600-650 °C, cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing and final vacuum annealing the worked ingot at 460-540 °C, which can be applied to the core components in a light water and a heavy water atomic reactor type nuclear power plant.

    摘要翻译： 本发明涉及一种具有优异的耐腐蚀性和机械性能以及用于通过锆合金制备核燃料包覆管的方法的锆合金。 更格外地，本发明涉及一种锆合金Zr的含有ANB-AAS-CFE DCR ECU（A = 0.05-0.4重量％，B = 0.3〜0.7％（重量），C = 0.1-0.4％（重量），D = 0-0.2％（重量）和e = 0.01〜0.2重量％，提供确实的Nb + SN = 0.35-1.0重量％），以及制备锆合金的核燃料包覆管，包括熔化的金属混合物，其包含的一个方法 锆和合金元素，以获得铸块，锻造在β相范围的锭，β--quenching锻造锭在1015至1075年℃，热加工在600-650℃下骤冷的锭，冷加工热加工锭 计划在三到五遍，与中间真空退火和最终真空退火在460-540℃下的加工锭，其可以在光水和重水原子反应堆类型核电被施加到核心组件。

    Zirconium alloy composition having excellent corrosion resistance for nuclear applications and method of preparing the same
    6.
    发明公开
    Zirconium alloy composition having excellent corrosion resistance for nuclear applications and method of preparing the same 有权
    具有核应用和它们的制备方法优异的耐腐蚀性Zirkoniumlegierungszusammensetzung

    公开(公告)号：EP1930454A1

    公开(公告)日：2008-06-11

    申请号：EP07075310.8

    申请日：2007-04-25

    申请人： Korea Atomic Energy Research Institute ,  Korea Hydro & Nuclear Power Co., Ltd.

    发明人： Jeong, Yong Hwan ,  Choi, Byoung Kwon ,  Baek, Jong Hyuk ,  Lee, Myung Ho ,  Park, Sang Yoon ,  Park, Jeong Yong ,  Kim, Jun Hwan ,  Kim, Hyun Gil

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

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

    摘要： The present invention relates to a zirconium alloy composition having excellent corrosion resistance for nuclear applications and a method of preparing the same. The zirconium alloy composition having excellent corrosion resistance for nuclear applications includes 1.3~2.0 wt% of niobium, 0.05~0.18 wt% of iron, 0.008~0.012 wt% of silicon, 0.008~0.012 wt% of carbon, and 0.1~0.16 wt% of oxygen, with the balance being zirconium, or includes 2.8~3.5 wt% of niobium, 0.2~0.7 wt% of at least one of iron and copper, 0.008~0.012 wt% of silicon, 0.008~0.012 wt% of carbon, and 0.1~0.16 wt% of oxygen, with the balance being zirconium. The present invention further relates to a method of preparing the zirconium alloy composition as described above, as well as high burn-up nuclear fuel cladding tubes, nuclear fuel assembly support grids and structural components of nuclear power plants made therefrom. The invention further relates to a method of preparing a zirconium alloy composition as described above, as well as high burn-up nuclear fuel cladding tubes, nuclear fuel assembly support grids and structural components of nuclear power plants made therefrom.

    摘要翻译： 本发明涉及一种具有用于核应用优异的耐腐蚀性及其制备的方法的锆合金组合物。 具有用于核应用优良的耐腐蚀性的锆合金组合物包含铌的1.3〜2.0％（重量），铁为0.05〜0.18重量％，硅的0.008〜0.012重量％，碳为0.008〜0.012重量％，和0.1〜0.16重量％的 氧，余量为锆，或包括铌的2.8〜3.5％（重量），铁和铜中的至少一种为0.2〜0.7重量％，硅的0.008〜0.012重量％，碳为0.008〜0.012重量％，且 的0.1〜0时16重量％的氧，余量为锆。 本发明还涉及制备该锆合金组合物，如上所述，以及高燃耗核燃料包覆管，核燃料组件支撑栅格和由其制成的核电厂的结构部件的方法。 本发明进一步涉及一种制备锆合金组合物，如上所述，以及高燃耗核燃料包覆管，核燃料组件支撑栅格和由其制成的核电厂的结构部件的方法。