Effect of titanium doping on deuterium behaviour in tungsten under low-energy deuterium plasma irradiation

Xia, Tongjun; Yan, Jing; Ye, Xiaoqiu; Wang, Zhanlei; Wu, Jiliang; Jiang, Zhi‐Qiang; Wang, Zizhao; Shi, Yongzhi; Han, Wenjia; Zhu, Kaigui

doi:10.1016/j.nimb.2022.03.009

Cited by 6 publications

(3 citation statements)

References 58 publications

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“…It should be pointed out that large amount of D atoms were trapped in the He irradiation layer (as mentioned in section (i)), and these D atoms will cause the He irradiation layer to swelling. The lateral stresses are produced by swelling and the lateral restraint imposed by the underlying W substrate [26][27][28][34][35][36]. The combination between the He irradiation layer and underlying W substrate was weakened (as mentioned in section (ii)), leading to a decrease of the lateral stresses.…”

Section: Inhibition Of Surface Blistering On W Followed By D Plasma E...mentioning

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.

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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: Inhibition Of Surface Blistering On W Followed By D Plasma E...mentioning

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.

Self Cite

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“…As the exposure time increased, the lateral stress increased and reached the fracture toughness of W [29]. In this way, the cracking would occur at the weakest points in the W, such as defects [10][11][12]. Then the stress was released by plastic deformation.…”

Section: Surface Topography Of Samples After D Plasma Exposurementioning

confidence: 99%

“…As the PFMs, W will inevitably be irradiated by high-density hydrogen isotope plasma and undergo serious surface modification. Previous research has shown that surface blistering [6][7][8][9][10][11][12], melting [13] and cracking [13] occurred on the W under deuterium (D) irradiation. These are detrimental to the properties of W. In order to study the underlying physical mechanism of surface blistering and hydrogen retention in W, a series of experiments were carried out.…”

Section: Introductionmentioning

confidence: 99%

Effect of anisotropic grain boundaries on the surface blistering of tungsten induced by deuterium plasma exposure

Xia¹,

Jiang²,

Shi³

et al. 2022

Phys. Scr.

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The effect of anisotropic grain boundaries on the surface microstructure changes and deuterium retention behavior in tungsten under deuterium plasma irradiation were studied. The samples named as NDW and RDW were cut from RD × TD plane and TD × ND plane of a rolled W plate (ND: normal direction, RD: rolling direction, TD: transverse direction), respectively. The results suggest that both surface morphology and deuterium retention in the RDW samples are suppressed compared to that of NDW samples for 1 h and 25 h deuterium irradiation. For 1 h exposure, the total deuterium retention in the NDW samples is about 1.6 times as much as that of RDW. However, as the exposure time increased to 25 h, the total deuterium retention in the NDW sample is two times the height of RDW sample. The experimental results show that the special grain structure of RDW can alleviate the surface morphology changes and decrease the deuterium retention in tungsten, which is interpreted by the lateral stress model of blistering.

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In silico monitoring of non-reactive gas blistering on crystalline substrates

Goh,

Li,

Park

et al. 2024

International Journal of Mechanical Sciences

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Effect of titanium doping on deuterium behaviour in tungsten under low-energy deuterium plasma irradiation

Cited by 6 publications

References 58 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

Effect of anisotropic grain boundaries on the surface blistering of tungsten induced by deuterium plasma exposure

In silico monitoring of non-reactive gas blistering on crystalline substrates

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