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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading
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Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading

机译:低应变速率拉伸载荷下位错通道对预辐照奥氏体不锈钢晶间微裂纹成核的影响建模

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In the present article, the effect of dislocation channel on intergranular microcrack nucleation during the tensile deformation of pre-irradiated austenitic stainless steels is studied. Because several slip planes are activated within the dislocation channel, the simple dislocation pile-up model seems not well suited to predict grain boundary stress field. Finite element computations, using crystal plasticity laws and meshes including a channel of finite thickness, are also performed in order to study the effect of some microstructural characteristics on grain boundary stress field. Numerical results show that: the thickness and the length of the dislocation channel influence strongly the grain boundary normal stress field. The grain boundary orientation with respect the stress axis does not affect so much the grain boundary normal stresses close to the dislocation channel. On the contrary far away the dislocation channel, the grain boundary stress field depends on the grain boundary orientation. Based on these numerical results, an analytical model is proposed to predict grain boundary stress fields. It is valuable for large ranges of dislocation channel thickness, length as well as applied stress. Then, a macroscopic microcrack nucleation criterion is deduced based on the elastic-brittle Griffith model. The proposed criterion predicts correctly the influence of grain boundary characteristics (low-angle boundaries (LABs), non-coincident site lattice (non-CSL) high-angle boundaries (HABs), special grain boundaries (GBs)) on intergranular microcrack nucleation and the macroscopic tensile stress required for grain boundary microcrack nucleation for pre-irradiated austenitic stainless steels deformed in argon environment. The criterion based on a dislocation pile-up model (Smith and Barnby) underestimates strongly the nucleation stress. These results confirm that pile-up models are not well suited to predict microcrack nucleation stress in the case of dislocation channels impacting grain boundary. The proposed criterion is applied to the prediction of the IASCC macroscopic nucleation stress for pre-irradiated material tested in PWR environment and the predictions are discussed with respect to experimental data. Finally, the limitations of the continuum modelling are discussed.
机译:本文研究了位错通道对预辐照奥氏体不锈钢拉伸变形过程中晶间微裂纹成核的影响。由于在位错通道内激活了多个滑动面,因此简单的位错堆积模型似乎不太适合预测晶界应力场。为了研究某些微结构特征对晶界应力场的影响,还使用晶体可塑性定律和包括有限厚度通道的网格进行了有限元计算。数值结果表明:位错通道的厚度和长度对晶界法向应力场影响很大。相对于应力轴的晶界取向对位错通道附近的晶界法向应力影响不大。相反,在位错通道很远的地方,晶界应力场取决于晶界取向。基于这些数值结果,提出了一种分析模型来预测晶界应力场。这对于位错通道的厚度,长度以及所施加的应力的较大范围都是有价值的。然后,基于弹性脆性格里菲斯模型推导了宏观的微裂纹成核判据。拟议的标准正确预测了晶界特征(低角度边界(LABs),非重合位点晶格(non-CSL)高角度边界(HABs),特殊晶粒边界(GBs)对晶间微裂纹成核的影响。氩环境下变形的预辐照奥氏体不锈钢晶界微裂纹成核所需的宏观拉伸应力。基于位错堆积模型(Smith和Barnby)的标准强烈低估了形核应力。这些结果证实,在位错通道影响晶界的情况下,堆积模型不太适合预测微裂纹成核应力。所提出的标准被应用于在预压水环境中测试的预辐照材料的IASCC宏观形核应力的预测,并针对实验数据讨论了该预测。最后,讨论了连续性建模的局限性。

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