Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

Sang, Chaofeng; Dai, Shuyu; Sun, Jizhong; Bonnin, X.; Xu, Qianfan; Ding, Fang; Wang, Dezhen

doi:10.1088/1674-1056/23/11/115201

Cited by 5 publications

(3 citation statements)

References 35 publications

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“…The theory calculation based on the empirical potential was used to investigate the stable configuration, migration path of SIA and vacancies. [9][10][11] Previous studies and our calculations suggested that 111 -type SIA configurations have the lowest formation energy in all nonmagnetic bcc metals [12,13] and the energy difference with that of the 110 dumbbell is about 0.28 eV. However, the ferromagnetic bcc α-Fe is fundamentally different from other bcc metals.…”

Section: Introductionmentioning

confidence: 54%

Stability of concentration-related self-interstitial atoms in fusion material tungsten

et al. 2016

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Based on the density functional theory, we calculated the structures of the two main possible self-interstitial atoms (SIAs) as well as the migration energy of tungsten (W) atoms. It was found that the difference of the 110 and 111 formation energies is 0.05-0.3 eV. Further analysis indicated that the stability of SIAs is closely related to the concentration of the defect. When the concentration of the point defect is high, 110 SIAs are more likely to exist, 111 SIAs are the opposite. In addition, the vacancy migration probability and self-recovery zones for these SIAs were researched by making a detailed comparison. The calculation provided a new viewpoint about the stability of point defects for selfinterstitial configurations and would benefit the understanding of the control mechanism of defect behavior for this novel fusion material.

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Section: Introductionmentioning

confidence: 54%

Stability of concentration-related self-interstitial atoms in fusion material tungsten

et al. 2016

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“…[28] and [29]: the plasma core and edge region, the scrape-off-layer (SOL) region, and the private flux and divertor plate region. [30] In the simulations, the fueling source is injected to the low field side of the HL-2A tokamak.…”

Section: Boundary Conditionsmentioning

confidence: 99%

Investigation of molecular penetration depth variation with SMBI fluxes

Zhou

Wang

et al. 2016

Chinese Phys. B

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We study the molecular penetration depth variation with the SMBI fluxes. The molecular transport process and the penetration depth during SMBI with various injection velocities and densities are simulated and compared. It is found that the penetration depth of molecules strongly depends on the radial convective transport of SMBI and it increases with the increase of the injection velocity. The penetration depth does not vary much once the SMBI injection density is larger than a critical value due to the dramatic increase of the dissociation rate on the fueling path. An effective way to improve the SMBI penetration depth has been predicted, which is SMBI with a large radial injection velocity and a lower molecule injection density than the critical density.

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“…Tungsten has been considered as one of the candidate PFMs for ITER because of its favorable physical and chemical properties, such as high thermal conductivity, high melting point, high-temperature mechanics performance, low physical and chemical sputtering yields, and no chemical reaction with hydrogen. [1][2][3][4][5][6][7] However, the brittleness of W material leads PFM to likely undergo crack failure when the transient event occurs. [8] W-Y 2 O 3 alloys can effectively impede the recovery and recrystallization at high temperature, and have low ductilebrittle transition temperature (DBTT) compared with pure tungsten.…”

Section: Introductionmentioning

confidence: 99%

Determination of activation energy of ion-implanted deuterium release from W-Y₂O₃*

Wang¹,

Wu²,

Li³

et al. 2020

Chinese Phys. B

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The retention and release of deuterium in W–2%Y2O3 composite materials and commercially pure tungsten after they have been implanted by deuterium plasma (flux ∼ 3.71 × 1021 D/m2⋅s, energy ∼ 25 eV, and fluence up to 1.3 × 1026 D/m2) are studied. The results show that the total amount of deuterium released from W–2%Y2O3 is 5.23 × 1020 D/m2(2.5 K/min), about 2.5 times higher than that from the pure tungsten. Thermal desorption spectra (TDS) at different heating rates (2.5 K/min–20 K/min) reveal that both W and W–2%Y2O3 have two main deuterium trapped sites. For the low temperature trap, the deuterium desorption activation energy is 0.85 eV (grain boundary) in W, while for high temperature trap, the desorption activation energy is 1.57 eV (vacancy) in W and 1.73 eV (vacancy) in W–2%Y2O3.

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Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

Cited by 5 publications

References 35 publications

Stability of concentration-related self-interstitial atoms in fusion material tungsten

Stability of concentration-related self-interstitial atoms in fusion material tungsten

Investigation of molecular penetration depth variation with SMBI fluxes

Determination of activation energy of ion-implanted deuterium release from W-Y₂O₃*

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Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

Cited by 5 publications

References 35 publications

Stability of concentration-related self-interstitial atoms in fusion material tungsten

Stability of concentration-related self-interstitial atoms in fusion material tungsten

Investigation of molecular penetration depth variation with SMBI fluxes

Determination of activation energy of ion-implanted deuterium release from W-Y2O3*

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Product

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Determination of activation energy of ion-implanted deuterium release from W-Y₂O₃*