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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Investigation of the thermo-mechanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory
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Investigation of the thermo-mechanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory

机译:自洽塑性理论研究中子辐照Fe-Cr合金的热机械行为

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摘要

The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elastic-viscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones. (C) 2016 Elsevier B.V. All rights reserved.
机译:通过自洽塑性理论研究了非辐照(223 K,302 K和573 K)和中子辐照(573 K)Fe-2.5Cr,Fe-5Cr和Fe-9Cr合金的热力学行为。 ,由描述辐射缺陷在晶粒水平上的贡献的本构方程以及获得多晶行为的弹性-粘塑性自洽方法组成。注意两种类型的辐射引起的缺陷:间隙位错环和富溶质团簇,它们被认为是中等辐照剂量下铁铬合金中硬化的主要来源。通过使用可用的微观结构实验数据并实施从原子数据得出的硬化规则,研究了硬化机理和微观结构演变。通过将位错环视为强热激活障碍,将富溶质团簇视为弱可剪切团簇,在未辐照和辐照的Fe-Cr合金的屈服应力和应变硬化方面均与实验数据良好吻合。 (C)2016 Elsevier B.V.保留所有权利。

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