In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten

被引:1
|
作者
Iroc, Koray [1 ,2 ]
Terentyev, Dmitry [1 ]
Van Renterghem, Wouter [1 ]
Dunatov, Toni [3 ]
Tadic, Tonci [3 ]
Klimenkov, Michael [4 ]
Baumier, Cedric [5 ]
Gentils, Aurelie [5 ]
Schryvers, Dominique [2 ]
机构
[1] Belgian Nucl Res Ctr, SCK CEN, Mol, Belgium
[2] Univ Antwerp, Dept Phys, EMAT, Antwerp, Belgium
[3] Rudjer Boskovic Inst, Zagreb, Croatia
[4] Karlsruhe Inst Technol, Inst Appl Mat, Karlsruhe, Germany
[5] Univ Paris Saclay, IJCLab, CNRS, IN2P3, Orsay, France
关键词
ITER; Tungsten; In-situ TEM; Ion irradiation; Fusion; DAMAGE; DEUTERIUM; ALLOYS; LOOPS;
D O I
10.1016/j.jnucmat.2024.155223
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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 degrees C, 800 degrees C, 900 degrees C and 1000 degrees 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.
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页数:10
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