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Evolution of Structural Materials in Nuclear Reactors

机译:核反应堆中结构材料的演变

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Structural materials used in conventional industry, their adoption and successive evolutions in the nuclear industry, from one generation of nuclear reactor to another, is presented. Specific examples for several steels are given, covering fabrication procedures, qualification methods, property databases and design allowable stresses, to show how the ever-increasing demands for better performance and reliability, in particular under neutron irradiation, have been met.rnParticular attention is paid to the austenitic stainless steels types 304L, 316L, 316L(N), 316L(N)-IG, titanium stabilised grade 321, precipitation strengthened Alloy 800, conventional and low activation ferritic/martensitic steels and their ODS derivatives. For each material, evolution of the associated filler metal and welding techniques is also presented.
机译:介绍了常规工业中使用的结构材料,它们在核工业中的应用以及从核反应堆的一代到另一代的不断发展。给出了几种钢材的具体示例,涵盖了制造程序,鉴定方法,性能数据库和设计允许应力,以说明如何满足对不断提高的性能和可靠性(特别是在中子辐照下)不断增长的要求。适用于304L,316L,316L(N),316L(N)-IG型奥氏体不锈钢,钛稳定级321,沉淀强化合金800,常规和低活化铁素体/马氏体钢及其ODS衍生物。对于每种材料,还介绍了相关的填充金属和焊接技术的发展。

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