Blistering and deuterium retention in Nb-doped W exposed to low-energy deuterium plasma

Han, Wenjia; Zhu, Kaigui; Yan, Jing; Xia, Tongjun; Wang, Zhanlei; Ye, Xiaoqiu; Chen, Chang An; Wu, Jiliang; Ma, Yutian

doi:10.1016/j.nme.2020.100741

Cited by 5 publications

(5 citation statements)

References 73 publications

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“…In the case of using D 2 plasma, the SEM results showed an interesting result, i.e., the appearance of blistering phenomena, which are specific to deuterium plasma behavior [21][22][23][24]. Compared with the results obtained in the hydrogen plasma exposure case, and also in argon and helium plasma cases from our previous work [28], here, the deuterium plasma seemed to be stable at the margin zones of the tungsten plate, and not in the central part.…”

Section: Tungsten Surfaces Exposed To H 2 and D 2 Plasmasupporting

confidence: 52%

“…Taking into account the nature of the used gases, for the proposed fusion reaction (deuterium and tritium), it is worth mentioning the highlighted lab-scale experiments concerning diffusivity inside bulk materials, for example, in the case of deuterium. In this line, labscale experiments were conducted for both hydrogen and low-energetic deuterium plasma in order to establish the mechanisms of various phenomena, such as blistering, which lead to tungsten surface damage and further promotes the formation of dust and various structures capable of entrapping tritium [17][18][19][20][21][22][23][24][25][26]. Keeping the various issues related to the fusion facilities in mind, it is mandatory to engage in lab-scale plasma experiments with fusion-relevant gases and materials in order to understand the starting point of the occurrence of dust, for example, blistering, melting, evaporation, sputtering, etc.…”

Section: Introductionmentioning

confidence: 99%

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Low-Temperature H2/D2 Plasma–W Material Interaction and W Dust Production for Fusion-Related Studies

et al. 2023

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In this paper, results concerning hydrogen and deuterium plasma (RF, 13.56 MHz) interactions with tungsten surfaces, were reported. We used the Hollow-Cathode (HC) configuration for plasma–tungsten surface interaction experiments, along with the collection of tungsten dust, at different distances. Further on, the plasma-exposed tungsten surfaces and the collected dust were morphologically analyzed by contact profilometry, scanning electron microscopy, and energy dispersive spectroscopy measurements, along with chemical investigations by the X-ray photoelectron spectroscopy technique. The results showed that exposing the tungsten surfaces to the hydrogen plasma induces surface erosion phenomena along with the formation of dust and interconnected W structures. Herein, the mean ejected material volume was ~1.1 × 105 µm3. Deuterium plasma facilitated the formation of blisters at the surface level. For this case, the mean ejected material volume was ~3.3 × 104 µm3. For both plasma types, tungsten dust within nano- and micrometer sizes could be collected. The current study offers a perspective of lab-scaled plasma systems, which are capable of producing tungsten fusion-like surfaces and dust.

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Section: Tungsten Surfaces Exposed To H 2 and D 2 Plasmasupporting

confidence: 52%

Section: Introductionmentioning

confidence: 99%

Low-Temperature H2/D2 Plasma–W Material Interaction and W Dust Production for Fusion-Related Studies

et al. 2023

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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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“…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.

Self Cite

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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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Blistering and deuterium retention in Nb-doped W exposed to low-energy deuterium plasma

Cited by 5 publications

References 73 publications

Low-Temperature H2/D2 Plasma–W Material Interaction and W Dust Production for Fusion-Related Studies

Low-Temperature H2/D2 Plasma–W Material Interaction and W Dust Production for Fusion-Related Studies

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

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