Helium retention in tungsten under plasma and ion beam irradiation and its impact on surface morphology

Gasparyan, Yu. M.; Ryabtsev, S.; Ефимов, В. М.; Harutyunyan, Z.; Aksenova, A.S.; Poskakalov, A. G.; Kaziev, Andrey V.; Kharkov, M. M.; Огородникова, О. В.; Писарев, А. А.; Kanashenko, S.L.; Ivanov, Yu. D.

doi:10.1088/1402-4896/ab4068

Cited by 17 publications

(3 citation statements)

References 30 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Figure 12 shows the simulated data for the incubation dose obtained in the temperature range of 780-2100 K and is compared with the experimental data from the literature [4,5,12,25,34,[43][44][45][46][47][48][49][50][51][52][53][54][55][56]. The simulation values for the incubation dose are in good agreement with the experimental results observed through SEM.…”

Section: Analysis For Early Stages Of W Fuzz Growthsupporting

confidence: 64%

Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation

Niu

Cui

Dai

et al. 2023

Plasma Phys. Control. Fusion

View full text Add to dashboard Cite

Low energy, high flux He exposure of tungsten surface leads to the formation of surface nanostructures and severe morphology changes, which may eventually erode tungsten divertor and threaten the operation of the reactor. In this study, the response of polycrystalline W under low energy He+ irradiation at different temperatures has been investigated in order to analyze the early stage of nanostructure formation. It is found that the interactions of high-density over-pressured He bubbles result in the formation of surface stress layers. The significant effect of temperature on the surface stress leads to differences in the incubation dose of W fuzz growth. The interaction between the planar network and the underlying W matrix is weak under surface stress, and the W fuzz grows on the surface once the stress reaches a threshold. Thereafter, the tensile stress-driven cracking causes the three-dimensional growth of W nanofibers.

show abstract

Section: Analysis For Early Stages Of W Fuzz Growthsupporting

confidence: 64%

Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation

Niu

Cui

Dai

et al. 2023

Plasma Phys. Control. Fusion

View full text Add to dashboard Cite

show abstract

“…This is line with the results of valles et al [50], who reported the binding energies of a He atom to a mixed He n V m cluster depended on the m and n parameters. Gasparyan et al [51] reported similar results and found that helium has multiple desorption peaks. Besides, the desorption peaks of LGW are higher than those of SGW at the temperature ranged from 300 K to 1100 K.…”

Section: Internal Microstructure Of W Irradiated By High Energy He Ionsmentioning

confidence: 66%

Surface modification and helium release of tungsten irradiated by 40 keV helium ions

Xia,

Jiang,

Shi

et al. 2023

Phys. Scr.

View full text Add to dashboard Cite

The effects of grain boundaries and surface roughness on tungsten irradiated by 40 keV He ions with a flux of 1.6 × 1017 He+/(m2s) to a fluence of 6.6 × 1021 He/m2 at room temperature were investigated. It was found that rough surfaces can suppress the surface blistering on tungsten. This may be due to the grooves appeared on rough tungsten limiting crack growth, resulting in the release of helium. However, the influence of grain boundaries on denseness of blistering was not obvious except the difference in blistering cap. The number of blister with detached cap on large grain tungsten samples (LGW, with the grain size of ~50 µm) is more than that on small grain tungsten samples (SGW, with the grain size of ~5 µm). In addition, the effect of grain boundaries on helium retention in tungsten cannot be ignored. The total He release from SGW was 2.56 × 1021 He/m2, which was smaller than the value (4.10 × 1021 He/m2) of LGW.

show abstract

“…Our previous researches showed that many He blisters occurred on W under He ions implantation with the fluence of ∼1×10 22 He m −2 [9][10][11][12]. For He ions pre-implantation, once the implantation fluence exceeds 10 21 He m −2 , He blistering will be formed on the W surface [13], so the surface morphology evolution must be considered for the subsequent D exposure. In this work, W specimens were implanted first with 40 keV He ions with fluences of 6×10 20 He m −2 and 6.6×10 21 He m −2 at room temperature and then exposed to D plasma at 420 K. Before He ions implantations and D plasma exposure, the sample surface was marked by focused ion beam (FIB), so the surface morphology evolution can be observed almost in situ.…”

Section: Introductionsmentioning

confidence: 99%

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.

View full text Add to dashboard Cite

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.

show abstract

Helium retention in tungsten under plasma and ion beam irradiation and its impact on surface morphology

Cited by 17 publications

References 30 publications

Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation

Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation

Surface modification and helium release of tungsten irradiated by 40 keV helium ions

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

Contact Info

Product

Resources

About