首页> 外国专利> Designing fuel assembly, useful for light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression and choosing the alloys

Designing fuel assembly, useful for light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression and choosing the alloys

机译:设计适用于包含锆合金结构成分的轻水核反应堆的燃料组件,包括使用牵引/压缩来计算单轴约束并选择合金

摘要

Designing a fuel assembly for a light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression to which the components are subjected during the life of assembly; and choosing the alloys in which the components are made from the criteria i.e. those subjected to a constraint of axial compression or cross compression e.g. - 10 to - 20 MPa are made in an alloy of which the content of elements other than zirconium does not exceed 5%, and of which the content of tin is e.g. - 0.025. to 0.25% to - 0.05.%. Designing a fuel assembly for a light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction or compression to which those components are subjected during the life of assembly; and choosing the zirconium alloys in which the components are made from the criteria i.e. those subjected to a constraint of axial compression or cross compression () (- 10 to - 20 MPa), (0 to - 10 MPa), (0 to + 10 MPa) and (+ 10 to + 20 MPa), respectively, are made in an alloy of which the content of elements other than zirconium does not exceed 5%, and of which the content of tin is (- 0.025. to 0.25)% to (- 0.05.%), traces to (0.05.+ 1)%, (0.05.%) to (0.07+ 1%) and (0.5%) to (1.7%), respectively. An independent claim is included for a fuel assembly for a light-water nuclear reactor comprising the structural components in the zirconium alloy subjected to a constraint of axial compression or cross compression (), comprising the components, which are made of the alloys by applying the process.
机译:设计用于包含锆合金结构部件的轻水核反应堆的燃料组件,包括在组件的使用寿命期间使用牵引/压缩来计算单轴约束;并从标准中选择组成成分的合金,即那些受到轴向压缩或横向压缩约束的合金,例如用除锆以外的元素的含量不超过5%且锡的含量例如为10〜20MPa的合金制成。 -0.025。至0.25%至-0.05。%。设计用于包含锆合金结构部件的轻水核反应堆的燃料组件,包括在组件的使用寿命期间使用牵引或压缩来计算这些组件所承受的单轴约束;并从标准中选择要制成成分的锆合金,即受到轴向压缩或交叉压缩约束的合金()(-10至-20 MPa),(0至-10 MPa),(0至+ 10 (MPa)和(+ 10至+ 20 MPa)分别由一种合金制成,该合金中锆以外的元素含量不超过5%,锡的含量为(-0.025。0.25)%到(-0.05。%),分别跟踪到(0.05。+ 1)%,(0.05。%)到(0.07 + 1%)和(0.5%)到(1.7%)。包括针对轻水核反应堆的燃料组件的独立权利要求,该燃料组件包括在锆合金中经受轴向压缩或横向压缩的约束的结构组分(),该组分包括通过施加合金而由合金制成的组分。处理。

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