Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions

Harutyunyan, Z.; Gasparyan, Yu. M.; Ryabtsev, S.; Ефимов, В. М.; Огородникова, О. В.; Писарев, А. А.; Kanashenko, S.L.

doi:10.1016/j.jnucmat.2021.152848

Cited by 19 publications

(3 citation statements)

References 39 publications

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“…Figure 7 presents thermal desorption spectrum of He from W sample before H plasma exposure. For the low He fluence implantation, there are many separated peaks in the spectrum which in line with the results of Harutyunyan et al [38]. For the He implantation at high fluence, the peak located at 350 K can be attributed to the release of He atoms adsorbed on the W surface [11].…”

Section: Tds Spectral Of He Ions In Wsupporting

confidence: 88%

Evolution of surface morphology and helium bubble in tungsten under 40 keV helium ions implantation followed by deuterium plasma exposure

Xia¹,

Wang²,

Jiang³

et al. 2022

Phys. Scr.

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Surface morphology and internal microstructure of tungsten (W) pre-implanted by 40 keV mass-separated helium (He) ions with different fluences at room temperature were investigated in this work. The morphology Changes of the samples were analyzed almost in situ, by repetitively examined the specified irradiation area which is marked by focused ion beam technology. As the samples were implanted by He ion with a fluence of 6 × 1020 He/m2, no He blisters or other microstructures could be found on the surface. When the fluence reaches 6 × 1021 He/m2, a large number of He blisters with the size of ~1 µm were observed on the W specimens. For the results of the subsequent deuterium plasma exposure, instead of deuterium-induced blistering, no changes on the W surface which pre-irradiated by He ion irradiation at low fluence (6 × 1020 He/m2). Surprisingly, for He ions pre-implanted W with high fluence (6 × 1021 He/m2), almost all the He blisters were cracked and their lids even peeled off. It could be attributed to the lateral stress caused by subsequent D exposure. Moreover, the size of He bubbles was also increased under subsequent deuterium exposure, suggesting that He atoms can attract D atoms. No deuterium blisters were found on these samples which were pre-implanted with high and low fluences, suggesting that He ion pre implantation can effectively inhibit the surface blistering caused by deuterium exposure.

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Section: Tds Spectral Of He Ions In Wsupporting

confidence: 88%

Evolution of surface morphology and helium bubble in tungsten under 40 keV helium ions implantation followed by deuterium plasma exposure

Xia¹,

Wang²,

Jiang³

et al. 2022

Phys. Scr.

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“…These experimental results indicate that the He-rich regions can serve as effective traps for H. In contrast, the prior H atoms impose a weak influence of He retention [22,23]. It is noteworthy that He irradiation does not invariably decrease H-isotope retention in the bulk region [31,32]. For instance, Ialovega et al have observed that in BCC W pre-irradiated by He, D retention at the near surface alters little compared with the pristine W after annealing at relatively low temperature (below 900 K), indicating a weak influence of He on H-isotope retention [31].…”

Section: Introductionmentioning

confidence: 81%

Dynamic investigations on hydrogen–helium interaction around the vacancy in BCC iron from ab-initio calculations

Luo

Huang²,

Li³

et al. 2023

Nucl. Fusion

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Coexistence of hydrogen (H) and helium (He) under vacancy (V) supersaturation in the fusion environment alters the dynamic evolution of cavities and ultimately influences the swelling of structural materials. Herein, we investigate H-He interaction around a vacancy as one prototype trapping site for H and He in body-centered cubic (BCC) iron (Fe) utilizing ab-initio calculations from the thermal dynamics. First, we demonstrate the significantly stronger He-V interaction than H-V interaction by comparing the dynamic trapping and de-trapping of H with those of He. Furthermore, we confirm the repulsive H-He interaction around the vacancy by examining their hopping around H-He-V complexes. The prior He in the vacancy imposes weak influence on the dynamic trapping of H, while enhances H de-trapping. Due to the prior He, more H atoms can be accommodated in the vacancy resulting from larger H-H distances to attenuate repulsive H-H interaction. The dynamic trapping of He by the vacancy is weakly influenced even though the vacancy is densely coated by the prior H. There exists a critical density of the prior H in the vacancy, below which the prior H enhances He de-trapping. Above this critical density, He de-trapping is inhibited by the prior H. This work provides significant dynamic insights at the atomic scale towards a better understanding of the cavity nucleation and H-isotopes/He retention in structural materials in the fusion environment.

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“…Hence, it is feasible to study the effect of He existence in tungsten bulk on D retention in tungsten using high-energy He ions irradiation. Several studies observed the increase in D retention in high-energy He ions irradiated tungsten, and found that this is caused by additional D trapping sites produced by displacement damage and He bubbles [16][17][18][19]. Moreover, a few studies focused on the synergistic effects of displacement damage and bulk He existence on D retention in tungsten.…”

Section: Introductionmentioning

confidence: 99%

Deuterium retention in heavy-ion and helium-ion sequentially irradiated tungsten

Zhang,

et al. 2024

Nucl. Fusion

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Neutron irradiation as well as the presence of helium (He) significantly affects fuel inventory in plasma-facing materials. To investigate the synergistic effects of neutron and He irradiation on deuterium (D) retention behaviors in tungsten, heavy- and He-ion sequentially irradiation experiments were performed with various He fluence and/or heavy-ion damage levels, and then the samples were exposed to low-energy D plasmas at 450 K. It is shown that even a low He concentration of 0.5 appm increases D concentration in the heavy-ion damaged region, which increases further with increasing He concentration under the parameters selected in this work (up to a maximum He concentration of 2.1 appm). The total D inventory in tungsten bulk also increases with He fluence due to the increase in D concentration both in the heavy-ion damaged region and the region irradiated by He-ion only. Furthermore, heavy-ion and He-ion successive irradiation slightly increases D retention in tungsten compared to the individual He ions irradiation. Similar to single heavy-ion damaged tungsten, the saturation of D retention is observed as heavy-ion irradiation damage above 0.2 dpa at a fixed He fluence.

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Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions

Cited by 19 publications

References 39 publications

Evolution of surface morphology and helium bubble in tungsten under 40 keV helium ions implantation followed by deuterium plasma exposure

Evolution of surface morphology and helium bubble in tungsten under 40 keV helium ions implantation followed by deuterium plasma exposure

Dynamic investigations on hydrogen–helium interaction around the vacancy in BCC iron from ab-initio calculations

Deuterium retention in heavy-ion and helium-ion sequentially irradiated tungsten

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