Effects of temperature on surface modification of W exposed to He particles

Li, C.; Greuner, H.; Yuan, Yue; Luo, Guang–Nan; Böswirth, B.; Fu, Baoqin; Xu, HY; Jia, Y.Z.; Liu, W.

doi:10.1016/j.jnucmat.2014.06.008

Cited by 21 publications

(15 citation statements)

References 16 publications

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“…After He loading at a peak surface temperature of 900 °C with a fluence of 1 × 10 22 m -2 , a large number of blisters are observed on the exposed surface, as shown in Figure 3. Blistering on W is widely reported in previous study [17][18][19]. Blistering on the W-5V shows some differences due to the three typical phase regions.…”

Section: Surface Modification After He Loading At a Peak Surface Tempmentioning

confidence: 71%

Surface modification of W–V alloy exposed to high heat flux helium neutral beams

Wang

Yuan

et al. 2018

Nucl. Fusion

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Surface modification of tungsten vanadium (W-V) alloy under high heat flux helium particle bombardment has been studied. W-5 wt.% V samples were irradiated by the repeated helium pulses at a peak surface temperature of 900 °C and 1800 °C, respectively, in the neutral beam facility GLADIS. The effect of helium fluence on the surface morphology changes was investigated by increasing helium fluence from 1 × 10 22 m-2 to 2 × 10 22 m-2. Blister is the typical structure after the repeated helium pulses loading at 900 °C, and it gets more severe with the increased fluence. Porous structure turns to be dominant at 1800 °C. An evolution of porous structure to coral-like structure is observed as fluence increases. In addition, the three typical regions in W-5V, W-enriched region, W-V solid solute region and V-enriched region, exhibit different damage features. W-V solid solute region shows better surface damage resistance compared to the other two regions.

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Section: Surface Modification After He Loading At a Peak Surface Tempmentioning

confidence: 71%

Surface modification of W–V alloy exposed to high heat flux helium neutral beams

Wang

Yuan

et al. 2018

Nucl. Fusion

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“…The changes in W surface microstructures under high-flux He + irradiation have been described previously [12,18,19]. The surface damage processes are diffusion-controlled, and strongly influenced by surface temperature [19]. Under a rather high surface temperature (>1000 K) condition, He nanobubbles rapidly grow by thermally migrating and coalescing with each other, and push up the surface, leading to the formation of nano-fuzzes [18].…”

Section: Discussionmentioning

confidence: 86%

Section: Discussionmentioning

confidence: 88%

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High-flux He+ irradiation effects on surface damages of tungsten under ITER relevant conditions

Liu

Hong

et al. 2016

Journal of Nuclear Materials

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A large-power inductively coupled plasma source was designed to perform the continuous helium ions (He +) irradiations of polycrystalline tungsten (W) under International Thermonuclear Experimental Reactor (ITER) relevant conditions. He + irradiations were performed at He + fluxes of 2.310 21-1.610 22 /m 2 s and He + energies of 12-220 eV. Surface damages and microstructures of irradiated W were observed by scanning electron microscopy. This study showed the growth of nano-fuzzes with their lengths of 1.3-2.0 m at He + energies of >70 eV or He + fluxes of >1.310 22 /m 2 s. Nanometer-sized defects or columnar microstructures were formed in W surface layer due to low-energy He + irradiations at an elevated temperature (>1300 K). The diffusion and coalescence of He atoms in W surface layers led to the growth and structures of nano-fuzzes. This study indicated that a reduction of He + energy below 12-30 eV may greatly decrease the surface damage of tungsten diverter in the fusion reactor.

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“…It has been indicated that the functional properties and structure performance of W in terms of particle irradiation resistance [8][9][10][11][12][13][14][15][16][17], surface morphology after irradiation [18][19][20][21], thermal conductivity [22] and fracture toughness [23] were related to its crystal orientation. Specifically, W grains with low crystallographic index displayed better irradiation resistance under deuterium plasma [8], helium neutral beam [9], helium/ hydrogen ions [10] and Ga + ion [11].…”

Section: Introductionmentioning

confidence: 99%

Texture evolution of tungsten materials during recrystallization

Zhang¹,

Zheng²,

Huang³

et al. 2020

Mater. Res. Express

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Some functional and structural performance of tungsten (W) are related to its texture characteristics. Usually, W serves in high temperature and may undergo recrystallization. Thus it's necessary to evaluate the recrystallization texture of W. In our previous studies, pure W (PW) and W-1.0wt%La 2 O 3 (WL10) were deformed via unidirectional rolling (UNR), cross rolling (CRR) and clock rolling (CLR) with 80% reduction. In the present paper, PW-UNR, PW-CRR, PW-CLR and WL10-UNR were subjected to annealing at 2073 K for 2 h to achieve recrystallization and figure out the evolution mechanism of recrystallization texture in W materials. Besides, the effect of La 2 O 3 on recrystallization texture of W was discussed. The results indicated that the fiber textures in rolling state were transformed into isolated textures after recrystallization. {001}〈uvw〉 isolated texture formed in the recrystallized W may be mainly resulted from the texture inheritance. {113}〈361〉 isolated texture formed in the recrystallized WL10-UNR may be attributed to the orientated growth of {113}〈361〉 grains with high grain boundary mobility facilitated by La 2 O 3 . Generally, isolated textures near θ-fiber were strengthened while γ-fiber was weakened for W during recrystallization, which is an effective method to achieve W with more {001} and less {111} textures.

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Effects of temperature on surface modification of W exposed to He particles

Cited by 21 publications

References 16 publications

Surface modification of W–V alloy exposed to high heat flux helium neutral beams

Surface modification of W–V alloy exposed to high heat flux helium neutral beams

High-flux He+ irradiation effects on surface damages of tungsten under ITER relevant conditions

Texture evolution of tungsten materials during recrystallization

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