Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation

SCRIPTA MATERIALIA

卷:180

Article

El-Atwani, O.¹  Cunningham, W. S.²  Perez, D.³  Martinez, E.³  Trelewicz, J. R.^2,4  Li, M.⁵  Maloy, S. A.¹ 

[1] Los Alamos Natl Lab, Mat Sci & Technol Div, Los Alamos, NM 87545 USA

[2] SUNY Stony Brook, Dept Mat Sci & Chem Engn, Stony Brook, NY 11794 USA

[3] Los Alamos Natl Lab, Theoret Div, Los Alamos, NM USA

[4] SUNY Stony Brook, Inst Adv Computat Sci, Stony Brook, NY 11794 USA

[5] Argonne Natl Lab, Div Nucl Engn, 9700 S Cass Ave, Argonne, IL 60439 USA

关键词: Grain boundaries;    Implantation;    In-situ;    Helium-vacancy complexes;    Electron microscopy;   

DOI  :  10.1016/j.scriptamat.2020.01.013

来源: Elsevier

【 摘 要 】

Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. Here, we investigate the radiation tolerance in terms of helium bubble damage in tungsten irradiated in-situ with 16 keV helium at 1073 K and 1223 K. Damage evolution represented by helium bubble density, size and total change in volume in the grain matrices and the grain boundaries are quantified as a function of fluence. Preferential large bubble formation and a higher change in volume on the grain boundaries occurred at 1223 K, suggesting faster migration of certain helium-vacancy complexes as confirmed by a diffusion-reaction model. Published by Elsevier Ltd on behalf of Acta Materialia Inc.

【 授权许可】

Free