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Multiscale modeling of irradiation hardening: Application to important nuclear materials
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2018-06-13 , DOI: 10.1016/j.jnucmat.2018.06.020
Ghiath Monnet

The recent progress in investigation techniques and the accumulation of relevant simulation results across the scales allow the development of a multiscale modeling framework for the rationalization, analysis and physical assessment of the flow stress of many industrial materials, with almost no fitting parameters. Although the construction of this framework is not yet complete, it has reached a maturity level enabling the investigation of some complex properties such as irradiation hardening. In this paper, modeling and experimental results are reviewed in order to derive the constitutive equations of the yield stress and of its fundamental components accounting for the microstructure features, such as dislocation network, precipitates, dislocation loops and voids. This approach is challenged in the case of reactor pressure vessel, high-Cr ferritic-martensitic and austenitic stainless steels. Predictions are discussed in connection with the well-known experimental trends reported in the literature.



中文翻译:

辐射硬化的多尺度建模:在重要核材料中的应用

研究技术的最新进展以及跨尺度的相关模拟结果的积累,使得可以开发出多尺度建模框架,以对许多工业材料的流应力进行合理化,分析和物理评估,而几乎没有合适的参数。尽管此框架的构建尚未完成,但已达到成熟水平,可以研究某些复杂的属性,例如辐射硬化。在本文中,对模型和实验结果进行了综述,以得出屈服应力及其基本成分的本构方程,这些本构方程考虑了位错网络,析出物,位错环和空隙等微观结构特征。对于反应堆压力容器,这种方法面临挑战,高铬铁素体-马氏体和奥氏体不锈钢。结合文献中报道的众所周知的实验趋势对预测进行了讨论。

更新日期:2018-06-13
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