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

Journal Article · · Scripta Materialia

Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. In this work, 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.

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy; USDOE Laboratory Directed Research and Development (LDRD) Program; National Science Foundation (NSF); G. T. Seaborg In- stitute; USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR). Scientific Discovery through Advanced Computing (SciDAC)
Grant/Contract Number:
AC02-06CH11357; AC07-05ID14517; 1810040; SC0008875; 89233218CNA000001
OSTI ID:
1641728
Alternate ID(s):
OSTI ID: 1595165; OSTI ID: 1657131
Report Number(s):
LA-UR-19-29529; 160843
Journal Information:
Scripta Materialia, Vol. 180; ISSN 1359-6462
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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