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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Plastic deformation of ferritic grains in presence of ODS particles and irradiation-induced defect clusters: A 3D dislocation dynamics simulation study
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Plastic deformation of ferritic grains in presence of ODS particles and irradiation-induced defect clusters: A 3D dislocation dynamics simulation study

机译:ODS颗粒和辐照缺陷簇存在下铁素体晶粒塑性变形:3D位错动力学模拟研究

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摘要

Ferritic steels strengthened by oxide particle dispersions (ODS) are prime candidate for future nuclear applications. So far, the beneficial mechanical characteristics of ODS steels are not fully understood, in terms of dislocation-based mechanisms. In this work, three-dimensional discrete dislocation dynamics simulations were carried out to analyze pre and post-irradiation plastic deformation in ferritic grains, with and without ODS particles. In the absence of irradiation induced defect loops, ODS-grains are stronger and plastic strain is more localized than in the corresponding, particle-free grain. After irradiation however, ODS-grain become more resistant to loop-induced hardening, while plastic strain spreading is broader, with respect to particle-free grain. This effect is due to dislocations accumulating next to the precipitates, generating internal stress allowing cross-slipped dislocations to go past the irradiation induced defect loops. Cross-slip is therefore a key feature of our model, for explaining the beneficial role of ODS particles on post-irradiation plastic deformation.
机译:通过氧化物颗粒分散体(ODS)增强的铁素体钢是未来核应用的主要候选材料。迄今为止,就基于位错的机理而言,ODS钢的有益机械特性尚未得到充分理解。在这项工作中,进行了三维离散位错动力学模拟,以分析在有和没有ODS颗粒的情况下,铁素体晶粒在辐照前后的塑性变形。在没有辐射引起的缺陷环的情况下,ODS晶粒比相应的无颗粒晶粒更坚固,塑性应变更局限。但是,在辐照后,相对于无颗粒的晶粒,ODS晶粒对环诱发的硬化具有更高的抵抗力,而塑性应变扩展更广。这种作用是由于位错在沉淀物附近堆积,产生了内部应力,从而使横向滑动的位错经过了辐照引起的缺陷环。因此,交叉滑动是我们模型的关键特征,用于解释ODS颗粒对辐照后塑性变形的有益作用。

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