Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental–numerical approach

Abstract This study employs an integrated experimental–numerical approach to assess the microstructural evolution of irradiation-induced defects in tungsten (W), which is being considered for fusion applications. A cluster dynamics (CD) model is utilized, and simulations are performed for irradiated disk-shaped compact tension W specimens. Experimental results indicate that the primary irradiation-induced defects in W at temperatures of 400 °C and 600 °C include dislocation loops (½<111> and <100>) and voids. Both experimental and CD results reveal that, at higher temperatures, the ½<111> loop population surpasses that of <100> loops, primarily due to the higher formation free energy of <100> loops compared to ½<111> loops. Given the high mobility of ½<111> loops in W, in the absence of traps, most ½<111> loops are absorbed by sinks or coalesce with <100> loops, leading to a reduced ½<111> loop population, as supported by the CD model. However, the introduction of traps results in an increased ½<111> loop population. The long-term evolution of loops demonstrates that the interaction between ½<111> and <100> loops facilitates the transfer of self-interstitial atoms between loops with different Burgers vectors, causing shifts in the populations of both loop types. The CD model reliably predicts the irradiation-induced microstructure in neutron-irradiated W, considering loops, voids and C15 clusters, while integrating the current state-of-the-art knowledge on radiation damage evolution and W energetics.

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Publication Details

Journal
Nuclear Fusion
Published
2025-04-24
DOI
https://doi.org/10.1088/1741-4326/add027
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.52
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article

Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental–numerical approach

Jarir Aktaa, D. Terentyev, Qian Yuan, Jie Gao et al.
1 citations
Nuclear Fusion
Fusion materials and technologies
0.52
article

Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental–numerical approach

Jarir Aktaa, D. Terentyev, Qian Yuan, Jie Gao, Salahudeen Mohamed, E. Gaganidze, D. Litvinov, H. Schneider
article en
1 citations

Abstract

Abstract This study employs an integrated experimental–numerical approach to assess the microstructural evolution of irradiation-induced defects in tungsten (W), which is being considered for fusion applications. A cluster dynamics (CD) model is utilized, and simulations are performed for irradiated disk-shaped compact tension W specimens. Experimental results indicate that the primary irradiation-induced defects in W at temperatures of 400 °C and 600 °C include dislocation loops (½<111> and <100>) and voids. Both experimental and CD results reveal that, at higher temperatures, the ½<111> loop population surpasses that of <100> loops, primarily due to the higher formation free energy of <100> loops compared to ½<111> loops. Given the high mobility of ½<111> loops in W, in the absence of traps, most ½<111> loops are absorbed by sinks or coalesce with <100> loops, leading to a reduced ½<111> loop population, as supported by the CD model. However, the introduction of traps results in an increased ½<111> loop population. The long-term evolution of loops demonstrates that the interaction between ½<111> and <100> loops facilitates the transfer of self-interstitial atoms between loops with different Burgers vectors, causing shifts in the populations of both loop types. The CD model reliably predicts the irradiation-induced microstructure in neutron-irradiated W, considering loops, voids and C15 clusters, while integrating the current state-of-the-art knowledge on radiation damage evolution and W energetics.

Nuclear FusionVol. 65(6)
Karlsruhe Institute of Technology (DE), Fudan University (CN), Belgian Nuclear Research Centre (BE), Institute of Modern Physics (CN)
Openalex Percentile: Top 39%
Fusion materials and technologies
0.52
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