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Proton irradiation for radiation-induced changes in microstructures and mechanical properties of austenitic stainless steel
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2018-11-14 , DOI: 10.1016/j.jnucmat.2018.11.017
Hyung-Ha Jin , Seong Sik Hwang , Min Jae Choi , Gyeong-Geun Lee , Junhyun Kwon

We report on microstructural and mechanical property changes as a function of radiation damage value in proton-irradiated austenitic stainless steel by means of advanced characterization techniques. The microstructural changes in proton-irradiated austenitic stainless steel were analyzed by transmission electron microscopy for observation of radiation-induced defects as well as the measurement of the chemical composition at grain boundaries. The radiation hardening after the proton irradiation was characterized by nano indentation for changes in hardness profiles with radiation damage.

Various transition points for microstructural and mechanical property changes under proton irradiation are analyzed via material characterization of proton-irradiated austenitic stainless steels. The saturation is expected to occur at approximately 10 displacements per atom (dpa) for the radiation-induced segregation of Cr, Ni, and P and approximately 2.5 dpa for radiation hardening. The cavity formation is observed to occur at hydrogen concentration levels greater than 5E5 atomic parts per million (appm) H. It is also found that the transition from black dot to Frank loop happened above approximately 1 dpa.

Profiles of radiation-induced segregation and radiation hardening as a function of dpa can be extended to the high irradiation condition, and can be compared with experimental data for neutron irradiation-induced segregation and radiation hardening. The radiation-induced segregation after the proton irradiation at 360 °C are in good agreement with that after neutron irradiation. On the other hand, it is observed that the evolution of radiation-induced defects and the corresponding radiation hardening exhibit sooner, that appears to be because of the dose rate effect.



中文翻译:

质子辐照用于辐射诱发的奥氏体不锈钢的显微组织和力学性能变化

我们通过先进的表征技术报告了质子辐照奥氏体不锈钢的微观结构和力学性能变化与辐射损伤值的关系。通过透射电子显微镜分析质子辐照奥氏体不锈钢的微观结构变化,以观察辐射诱发的缺陷以及晶界处的化学成分的测量。质子辐照后的辐照硬化以纳米压痕为特征,用于随着辐照损伤而改变硬度分布。

通过质子辐照奥氏体不锈钢的材料表征,分析了质子辐照下微观结构和力学性能变化的各种转变点。对于辐射诱导的Cr,Ni和P的偏析,预计饱和将发生在每原子约10个位移(dpa)处,而对于辐射硬化,则发生在约2.5 dpa处。观察到空穴形成发生在氢浓度高于百万分之5 H 5 E5原子份的水平上。还发现从黑点到Frank环的跃迁发生在大约1 dpa以上。

可以将辐射诱导的分离和辐射硬化的轮廓作为dpa的函数扩展到高辐照条件,并且可以与中子辐射诱导的分离和辐射硬化的实验数据进行比较。质子在360°C辐照后的辐射诱发偏析与中子辐照后的辐照偏析非常吻合。另一方面,观察到辐射诱发的缺陷的发展和相应的辐射硬化表现得更快,这似乎是由于剂量率效应引起的。

更新日期:2018-11-14
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