Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions

Sizyuk, T.; Abrams, T.

doi:10.1016/j.jnucmat.2022.154095

Cited by 6 publications

(3 citation statements)

References 47 publications

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“…The ITMC-DYN package computes the incident plasma particles interaction with materials and integrates Monte Carlo and deterministic models [10,14]. The package includes interatomic potential functions for detailed modeling of ion/atom collisions; models for the energy loss of elastic and inelastic collisions; particles thermal diffusion and segregation processes in near-surface layers, hydrogen isotope trapping, molecular surface recombination and desorption, chemical and physical erosion, and calculation of rate coefficients in multi-component materials based on the dynamic material composition.…”

Section: Review Of Coupled Modelsmentioning

confidence: 99%

“…All models are integrated in a self-consistent manner that allows accurate simulation of real experimental conditions and parameters, such as: multiple and simultaneous ions composition, energies, and fluxes; material characteristics and temperature; and the experimental setup. The integrated models have been extensively benchmarked with both in-house experiments and published data worldwide [10,14,15]. The ITMC-DYN package is continuously being upgraded and enhanced for the analysis of PFMs in fusion reactor environments.…”

Section: Review Of Coupled Modelsmentioning

confidence: 99%

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Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors

Sizyuk,

Brooks,

Abrams

et al. 2024

Nucl. Fusion

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The performance of silicon carbide as an alternative plasma facing material (PFM) was studied at various irradiation conditions relevant to ion energies and fluxes of a fusion reactor. This analysis involves detailed modeling of subsurface plasma/material interactions, sputtered particle transport above the surface and redeposition, and related changes in material composition and microstructure induced by steady-state and Edge Localized Mode ion fluxes. Transition of a crystalline SiC surface to semi-crystalline and amorphous phases was analyzed based on advanced modeling of DIII-D tokamak experiments where SiC was irradiated in single- and multiple- L-mode and H-mode discharges. This analysis shows that displacement damage, particle deposition/redeposition, and D accumulation on the SiC divertor surface can lead to significant microstructural changes that result in enhanced sputtering erosion in comparison with the original crystalline material. However, the resulting total net erosion rate for a full-coverage, advanced tokamak, SiC coated divertor may well be acceptably low. Moreover, the C sputtering yield from the evolved SiC surface can be seven times lower than from a pure graphite surface; this would imply significantly reduced tritium co-deposition rates in a D-T tokamak reactor, compared with a pure carbon surface. It was also determined that chemical sputtering of both C and Si should not result in any noticeable effect on the net erosion, for attached plasma regimes. Our results thus show encouraging results overall for use of SiC as a PFM in tokamaks.

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Section: Review Of Coupled Modelsmentioning

confidence: 99%

Section: Review Of Coupled Modelsmentioning

confidence: 99%

Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors

Sizyuk,

Brooks,

Abrams

et al. 2024

Nucl. Fusion

Self Cite

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show abstract

“…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%

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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Impact of microwave plasma treatment on tritium retention in submicronic tungsten dust

Mărăscu

Payet

Garcia‐Argote

et al. 2023

International Journal of Hydrogen Energy

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Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions

Cited by 6 publications

References 47 publications

Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors

Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors

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

Impact of microwave plasma treatment on tritium retention in submicronic tungsten dust

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