Journal
SCRIPTA MATERIALIA
Volume 180, Issue -, Pages 6-10Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.scriptamat.2020.01.013
Keywords
Grain boundaries; Implantation; In-situ; Helium-vacancy complexes; Electron microscopy
Categories
Funding
- U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office as part of a Nuclear Science User Facilities experiment [DE-AC07-051D14517]
- Laboratory Directed Research and Development program of Los Alamos National Laboratory [20160674PRD3]
- National Science Foundation [1810040]
- U.S. Department of Energy through the LANL/LDRD Program
- G. T. Seaborg Institute
- U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences
- Office of Advanced Scientific Computing Research through the Scientific Discovery through Advanced Computing (SciDAC) project on Plasma -Surface Interactions [DE-SC0008875]
- Division Of Materials Research
- Direct For Mathematical & Physical Scien [1810040] Funding Source: National Science Foundation
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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.
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