Ion irradiation-induced localized stress relaxation in W thin film revealed by cross-sectional X-ray nanodiffraction

Hlushko, K.; Macková, Anna; Zálešák, Jakub; Burghammer, Manfred; Davydok, Anton; Krywka, Christina; Daniel, Rostislav; Keckes, Jozef; Todt, Juraj

doi:10.1016/j.tsf.2021.138571

Cited by 4 publications

(2 citation statements)

References 23 publications

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“…There are two competing mechanisms that are responsible for the different degrees of lattice swelling. First, lattice shrinkage can occur by the irradiation-induced relaxation of the non-equilibrium crystal structure that was formed during the physical vapor deposition process [63][64][65]. Second, the insertion of He atoms in the grains but outside of the He bubbles can make a lattice expansion, whose rate would depend upon the solutes.…”

Section: Resultsmentioning

confidence: 99%

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

Jo¹,

Park²,

You³

et al. 2022

Preprint

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One of the challenges in fusion reactors is the discovery of plasma facing materials capable of withstanding extreme conditions, such as radiation damage and high heat flux. Development of fusion materials can be a daunting task since vast combinations of microstructures and compositions need to be explored, each of which requires trial-and-error based irradiation experiments and materials characterizations. Here, we utilize combinatorial experiments that allow rapid and systematic characterizations of composition-microstructure dependent irradiation damage behaviors of nanostructured tungsten alloys. The combinatorial materials library of W-Re-Ta alloys was synthesized, followed by the high-throughput experiments for probing irradiation damages to the mechanical, thermal, and structural properties of the alloys. This highly efficient technique allows rapid identification of composition ranges with excellent damage tolerance. We find that the distribution of implanted He clusters can be significantly altered by the addition of Ta and Re, which play a critical role in determining property changes upon irradiation.

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Section: Resultsmentioning

confidence: 99%

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

Jo¹,

Park²,

You³

et al. 2022

Preprint

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“…Therefore, performing HR-XRD measurements to determine the local strain is not an option in polycrystal systems but only the average strain can be extracted . Recently, several studies focused on mapping the strain distribution employing a scanning synchrotron X-ray beam across thin lamellae. − Only a few papers focused on the spatial strain of indented and annealed virgin multilayers. − However, until now, no study has focused on local strain in an irradiated multilayer system. This study paves the way for quantitative predictions of the microstructure changes in hexagonal closest packing (HCP)/BCC multilayers, namely, Zr/Nb NMMs after irradiation under different conditions.…”

Section: Introductionmentioning

confidence: 99%

Interface-Driven Strain in Heavy Ion-Irradiated Zr/Nb Nanoscale Metallic Multilayers: Validation of Distortion Modeling via Local Strain Mapping

Sen

Daghbouj

Callisti

et al. 2022

ACS Appl. Mater. Interfaces

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Nanolayered metallic alloys are promising materials for nuclear applications thanks to their resistance to radiation damage. Here, we investigate the effect of ion (C, Si, and Cu) irradiation at room temperature with different fluences into sputtered Zr/Nb metallic multilayer films with periods 27 nm (thin) and 96 nm (thick). After irradiation, while a high strain in the entire thin nanoscale metallic multilayer (NMM) is observed, a quite small strain in the entire thick NMM is established. This difference is further analyzed by a semianalytical model, and the reasons behind it are revealed, which are also validated by local strain mapping. Both methods show that within a thick layer, two opposite distortions occur, making the overall strain small, whereas in a thin layer, all the atomic planes are affected by the interface and are subjected to only a single type of distortion (Nbtension and Zrcompression). In both thin and thick NMMs, with increasing damage, the strain around the interface increases, resulting in a release of the elastic energy at the interface (decrease in the lattice mismatch), and the radiation-induced transition of the Zr/Nb interfaces from incoherent to partially coherent occurs. Density functional theory simulations decipher that the inequality of point defect diffusion flux from the inner to the interface-affected region is responsible for the presence of opposite distortions within a layer. Technologically, based on this work, we estimated that Zr/Nb55 with thicknesses around Zr = 24 nm and Nb = 31 nm is the most promising multilayer system with the high radiation damage resistance and minimum swelling for nuclear applications.

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Combinatorial discovery of irradiation damage tolerant nano-structured W-based alloys

Park

You

et al. 2022

Journal of Nuclear Materials

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Ion irradiation-induced localized stress relaxation in W thin film revealed by cross-sectional X-ray nanodiffraction

Cited by 4 publications

References 23 publications

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

Interface-Driven Strain in Heavy Ion-Irradiated Zr/Nb Nanoscale Metallic Multilayers: Validation of Distortion Modeling via Local Strain Mapping

Combinatorial discovery of irradiation damage tolerant nano-structured W-based alloys

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