He bubble-driven growth of W fuzz during the interaction between H2/He plasmas and W materials

Ni, Weiyuan; Fan, Hongyu; Niu, Chunjie; Zhang, Yang; Liu, Lu; Cui, Yunqiu; Liu, Dongping

doi:10.1007/s42864-021-00096-4

Cited by 9 publications

(1 citation statement)

References 52 publications

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“…In HEA/W multilayers, since the interstitial formation energy of each element in HEA is lower than that of W interstitials in pure W [15], the growth of He bubbles at the interface are more inclined to squeeze into the HEA layer, the experimental phenomenon is shown in figure 5. As the number of SIAs increases, they tend to diffuse toward the surface or interface to decrease the system energy [47,48], forming adatoms on the surface. Cr and V were sputtered due to their low sputtering thresholds.…”

Section: Discussionmentioning

confidence: 99%

Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion

Qu,

Hong,

Wei

et al. 2024

Nucl. Fusion

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The performance of Plasma-facing materials (PFMs) is one of the key factors that significantly impact the stability of operation in fusion reactors. Herein, a new CrMoTaWV/W (HEA/W) multilayer structure is designed as PFM to investigate its resistance to He plasma irradiation. It was observed that the introduction of the interfaces effectively absorbed plenty of He atoms, preventing them from diffusing into the material and delaying the formation of fuzz incubation zone, therefore, enhancing the resistance to plasma irradiation. The thickness transformed to fuzz in the HEA/W multilayer films was observed to be about two-thirds of those in the CrMoTaWV (HEA) film. Additionally, the fuzz growth rates in HEA/W multilayer films are lower than the average growth rate of bulk W and HEA films. These findings highlight a promising new avenue for the exploration of high-performance PFMs.

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Section: Discussionmentioning

confidence: 99%

Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion

Qu,

Hong,

Wei

et al. 2024

Nucl. Fusion

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A review of late-stage tungsten fuzz growth

Wright

2022

Tungsten

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Tungsten will be used as the plasma-facing divertor material in the International Thermonuclear Experimental Reactor (ITER) fusion reactor. Under high temperatures and high ion fluxes, a ‘fuzz’ nanostructure forms on the tungsten surface with dramatically different properties and could contaminate the plasma. Although simulations and experimental observations have provided understanding of the initial fuzz formation process, there is debate over whether tungsten or helium migration is rate-limiting during late-stage growth, and the mechanisms by which tungsten and helium migrations occur. Here, the proposed mechanisms are considered in turn. It is concluded that tungsten migration occurs by adatom diffusion along the fuzz surface. Continual helium migration through the porous fuzz to the tungsten bulk is also required for fuzz growth, for continued bubble growth and rupture. Helium likely migrates due to ballistic penetration, although diffusion may contribute. It is difficult to determine the limiting process, which may switch from helium penetration to tungsten adatom diffusion above a threshold flux. Areas for further research to clarify the mechanisms are then considered. A greater understanding of the fuzz formation mechanism is key to the successful design of plasma-facing tungsten components, and may have applications in forming porous tungsten catalysts.

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Composite effect of helium ion irradiation and transient thermal shock on recrystallized pure W and W-Y2O3 alloys

Yang,

Wang,

Feng

et al. 2023

Fusion Engineering and Design

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He bubble-driven growth of W fuzz during the interaction between H2/He plasmas and W materials

Cited by 9 publications

References 52 publications

Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion

Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion

A review of late-stage tungsten fuzz growth

Composite effect of helium ion irradiation and transient thermal shock on recrystallized pure W and W-Y2O3 alloys

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