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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Mechanical properties and microstructure of advanced ferritic-martensitic steels used under high dose neutron irradiation
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Mechanical properties and microstructure of advanced ferritic-martensitic steels used under high dose neutron irradiation

机译:高剂量中子辐照下使用的高级铁素体-马氏体钢的力学性能和显微组织

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摘要

Some results of the study of mechanical properties and structure of ferritic-martensitic chromium steels with 13% and 9% chromium, irradiated in the BOR-60 reactor up to different damage doses are presented in this report. Results concerning the behaviour of commercial steels, containing to molybdenum, vanadium and niobium, and developed for the use in fusion reactors, are compared to low-activation steels in which W and Ta replaced Mo and Nb. It is shown that after irradiation to the dose of approx 10 dpa at 400 deg C 0.1C-9Cr-1W, V, Ta steels are prone to lower embrittlement as deduced from fracture surface observations of tensile specimes. Peculiarities of fine structure and fracture mode, composition and precipitation reactions in steels during irradiation are discussed.
机译:本报告介绍了在BOR-60反应堆中辐照不同损伤剂量的含13%和9%铬的铁素体-马氏体铬钢的力学性能和组织的一些研究结果。将涉及钼,钒和铌的商业钢的性能结果开发出来,并将其用于聚变反应堆中,并将其结果与其中W和Ta替代Mo和Nb的低活化钢进行了比较。结果表明,在400℃0.1C-9Cr-1W,V辐照剂量约为10 dpa后,Ta钢的脆性降低,这是从拉伸试样的断裂表面观察得出的。讨论了钢在辐照过程中的细微结构,断裂方式,成分和析出反应的特殊性。

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