Towards understanding the mechanism of rhenium and osmium precipitation in tungsten and its implication for tungsten-based alloys

被引:35
|
作者
Li, Yu-Hao [1 ,2 ]
Zhou, Hong-Bo [1 ,2 ]
Deng, Huiqiu [3 ]
Lu, Gang [4 ]
Lu, Guang-Hong [1 ,2 ]
机构
[1] Beihang Univ, Dept Phys, Beijing 100191, Peoples R China
[2] Beihang Univ, Beijing Key Lab Adv Nucl Mat & Phys, Beijing 100191, Peoples R China
[3] Hunan Univ, Sch Phys & Elect, Dept Appl Phys, Changsha 410082, Hunan, Peoples R China
[4] Calif State Univ Northridge, Dept Phys & Astron, Northridge, CA 91330 USA
基金
美国国家科学基金会; 中国国家自然科学基金;
关键词
Interstitial-mediated migration and aggregation; Radiation-induced precipitation; Tungsten; Alloying elements; W-RE ALLOYS; NEUTRON-IRRADIATED TUNGSTEN; ATOM-PROBE TOMOGRAPHY; MINIMUM ENERGY PATHS; ELASTIC BAND METHOD; MICROSTRUCTURAL DEVELOPMENT; 1ST-PRINCIPLES CALCULATIONS; AB-INITIO; DEUTERIUM RETENTION; POINT-DEFECTS;
D O I
10.1016/j.jnucmat.2018.03.035
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Using a first-principles method in combination with thermodynamic models, we investigate the interaction between rhenium/osmium (Re/Os) and defects to explore the mechanism of radiation-induced Re/ Os precipitation in tungsten (W). We demonstrate that radiation-induced defects play a key role in the solute precipitation in W, especially for self-interstitial atoms (SIAs). The presence of SIAs can significantly reduce the total nucleation free energy change of Re/Os, and thus facilitate the nucleation of Re/Os in W. Further, SIA is shown to be easily trapped by Re/Os once overcoming a low energy barrier, forming a W-Re/Os mixed dumbbell. Such W-Re/Os dumbbell forms a high stable Re/Os-Re/Os dumbbell structure with the substitutional Re/Os atoms, which can serve as a trapping centre for subsequent interstitial-Re/Os, leading to the growth of Re/Os-rich clusters. Consequently, an interstitial-mediated migration and aggregation mechanism for Re/Os precipitation in W has been proposed. Our results reveale that the alloying elements-defects interaction has significantly effect on their behaviors under irradiation, which should be considered in the design of W-based alloys for future fusion devices. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码:30 / 43
页数:14
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