TY - JOUR
T1 - In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten
AU - Iroc, Koray
AU - Terentyev, Dmitry
AU - Van Renterghem, Wouter
AU - Dunatov, Toni
AU - Tadić, Tonči
AU - Klimenkov, Michail
AU - Baumier, Cédric
AU - Gentils, Aurelie
AU - Schryvers, Dominique
N1 - Score=10
This work has been carried out within the framework of the EUROfusion Consortium and has
received funding from the Euratom research and training programme 2014-2018 and 2019-2020
under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect
those of the ITER Organization or of the European Commission. The work was partially supported
by the FOD fusion grant of Belgium government.
Publisher Copyright:
© 2024 Elsevier B.V.
PY - 2024/10
Y1 - 2024/10
N2 - The annealing of irradiation defects in tungsten was investigated under in-situ observations conducted using transmission electron microscopy (TEM). ITER-specification tungsten was exposed to heavy-ion irradiation by 10 MeV Au+ ions to 0.5 and 1 dpa at room temperature to generate defects. Subsequently, the thermal stability and recovery mechanisms of the generated defects are investigated by in-situ TEM at 600 °C, 800 °C, 900 °C and 1000 °C. The obtained TEM data are used to visualize and quantify the defect characteristics such as loops and voids as well as for observing the evolution of the microstructure and defect diffusion/recovery mechanisms. Focus is made on specific spatial phenomena such as loop-loop interaction, loop-dislocation and loop-grain boundary decoration, loop pinning, entanglement, formation of raft and transformation of loops into a dislocation network. The obtained results are in line with earlier obtained data for pure recrystallized tungsten, still, present results provide important information such as radiation-induced defect characteristics and recovery mechanisms under high temperature for the ITER-specification tungsten.
AB - The annealing of irradiation defects in tungsten was investigated under in-situ observations conducted using transmission electron microscopy (TEM). ITER-specification tungsten was exposed to heavy-ion irradiation by 10 MeV Au+ ions to 0.5 and 1 dpa at room temperature to generate defects. Subsequently, the thermal stability and recovery mechanisms of the generated defects are investigated by in-situ TEM at 600 °C, 800 °C, 900 °C and 1000 °C. The obtained TEM data are used to visualize and quantify the defect characteristics such as loops and voids as well as for observing the evolution of the microstructure and defect diffusion/recovery mechanisms. Focus is made on specific spatial phenomena such as loop-loop interaction, loop-dislocation and loop-grain boundary decoration, loop pinning, entanglement, formation of raft and transformation of loops into a dislocation network. The obtained results are in line with earlier obtained data for pure recrystallized tungsten, still, present results provide important information such as radiation-induced defect characteristics and recovery mechanisms under high temperature for the ITER-specification tungsten.
KW - ITER
KW - Tungsten
KW - In-situ TEM
KW - Ion irradiation
KW - Fusion
UR - http://www.scopus.com/inward/record.url?scp=85196302983&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2024.155223
DO - 10.1016/j.jnucmat.2024.155223
M3 - Article
SN - 0022-3115
VL - 599
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 155223
ER -