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Design method of a fuel assembly according optimized efforts use in a nuclear light water reactor

机译:一种优化努力的核燃料轻水堆燃料组件设计方法

摘要

Design method of a fuel assembly for nuclear light water reactor comprising structure components in zirconium alloy, characterized in that: - the traction or compression uniaxial stresses they are subjected such components during calculated the life of the assembly, - and zirconium alloys in which these components are made according the following criteria are selected: * the subject to an axial compression or transverse understood σ at -10 and -20 MPa will be made of an alloy whose content in different elements of Zr does not exceed 5%, and Sn content of which is between Sn = (-0.025 · σ - 0.25)% and Sn = -0.05 · σ * the% against stress axial compression or transverse σ comprised between 0 and -10 MPa will be made of an alloy whose content of different elements Zr not exceeding 5% and Sn content of which is understood ent re Sn = trace and Sn = (0.05 · σ + 1)% * subjected to the axial tensile stress σ or cross between 0 and +10 MPa will be made of an alloy whose content of different elements Zr not exceeding 5% and whose Sn content is between Sn = 0.05 · σ% and Sn = (0.07 · σ + 1)% * subjected to the axial tensile stress σ or cross between + 10 and +20 MPa will be made of an alloy whose content of different elements Zr not exceeding 5% and whose Sn content is between 0.50% and 1.70%.
机译:一种用于核轻水堆的燃料组件的设计方法,该燃料组件包括锆合金的结构部件,其特征在于:-在组件的寿命计算过程中,牵引或压缩单轴应力使这些部件承受这些部件;以及-锆合金,其中这些部件合金是根据以下标准选择的:*在-10和-20 MPa承受轴向压缩或横向σ的对象将由一种合金制成,该合金的Zr不同元素含量不超过5%,且Sn含量为Sn> =(-0.025·σ-0.25)%和Sn> = -0.05·σ*相对于轴向应力或横向σ的百分比介于0和-10 MPa之间的合金将由其含量不同的合金制成元素Zr不超过5%,且Sn含量应理解为Sn> =痕量且Sn> =(0.05·σ+ 1)%*将经受轴向拉伸应力σ或0到+10 MPa之间的交变含量不同的合金t元素Zr不超过5%且Sn含量在Sn> = 0.05·σ%和Sn> =(0.07·σ+ 1)%之间*承受轴向拉应力σ或在+ 10到+20 MPa之间交叉由不同元素Zr的含量不超过5%且Sn含量在0.50%至1.70%之间的合金制成。

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