Deuterium retention in W and binary W alloys irradiated with high energy Fe ions

Wang, Jing; Hatano, Yuji; Hinoki, Tatsuya; Alimov, V.Kh.; Спицын, А. В.; Bobyr, N. P.; Kondo, Sosuke; Toyama, Takeshi; Lee, H.T.; Ueda, Y.; Schwarz-Selinger, T.

doi:10.1016/j.jnucmat.2020.152749

Cited by 18 publications

(7 citation statements)

References 18 publications

(28 reference statements)

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“…Good agreement between the results obtained is observed with the recent work of Wang [7], in which a twofold decrease in the capture of deuterium in tungsten is also observed upon the introduction of 5 at% of tantalum. The samples, as in our experiment, were saturated from the gas phase at a pressure of 10 5 Pa and a temperature of 673 K. The authors explain the effect by a weaker bond between an interstitial tungsten atom and an impurity tantalum atom, based on theoretical calculations by Sudzo [8].…”

Section: Resultssupporting

confidence: 89%

“…This may be explained by the difference in sample preparation and the predominant capture of deuterium in a thin near-surface layer, which is polycrystalline in both studies. As it shown on the NRA spectras in [7] deuterium concentration in the near-surface region can reach up to 0,1 at%. Thus, it is shown that the contribution of deuterium retained in this layer significantly affects the total retention in undamaged experimental samples.…”

Section: Resultsmentioning

confidence: 59%

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Deuterium retention in W-Ta alloys after low-temperature plasma irradiation and gas exposure

Bobyr¹,

Ефимов²,

Khripunov³

et al. 2021

Phys. Scr.

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In this study plates of W, W-xTa alloys (x = 1; 3; 5 concentration in at.%) with a large grain size were used as experimental samples. All the samples were polished to a mirror surface and outgassed in vacuum at 1100 K during 2 hours. Sets of W, W-1Ta, W-3Ta, W-5Ta samples were irradiated with low-temperature D plasma up to fluences of 2e25 D/m2. Other sets of W, W-1Ta, W-3Ta, W-5Ta samples were exposed in D2 gas in a temperature range of 425625 K and pressure 103 Pa. The D retention in W and W-Ta alloys was measured by thermal desorption spectroscopy (TDS). An influence of Ta dopant on deuterium retention in W was observed. The dopant of tantalum slightly reduces the accumulation of deuterium in tungsten during gas exposure. Increasing temperature of samples during D-plasma irradiation from 415 K to 615 K reduces deuterium retention up to 2 orders of magnitude.

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Section: Resultssupporting

confidence: 89%

Section: Resultsmentioning

confidence: 59%

Deuterium retention in W-Ta alloys after low-temperature plasma irradiation and gas exposure

Bobyr¹,

Ефимов²,

Khripunov³

et al. 2021

Phys. Scr.

Self Cite

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“…Presently the separators are proposed to be in the divertor ports, before two sets of pumps (for the permeate and retentate). metals such as Re [74]). In principle this might be delayed by implanting deuterium initially, filling some of the traps.…”

Section: Integration Example 2: How To Provide Tritium To the Plasma ...mentioning

confidence: 99%

Towards a fusion power plant: integration of physics and technology

Morris

Akers

Cox

et al. 2022

Plasma Phys. Control. Fusion

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A fusion power plant can only exist with physics and technology acting in synchrony, over space (angstroms to tens of metres) and time (femtoseconds to decades). Recent experience with the European DEMO programme has shown how important it is to start integration early, yet go deep enough to uncover the integration impact, favourable and unfavourable, of the detailed physical and technological characteristics. There are some initially surprising interactions, for example, the fusion power density links the properties of materials in the components to the approaches to waste and remote maintenance in the context of a rigorous safety and environment regime. In this brief tour of a power plant based on a tokamak we outline the major interfaces between plasma physics and technology and engineering considering examples from the European DEMO (exhaust power handling, tritium management and plasma scenarios) with an eye on other concepts. We see how attempting integrated solutions can lead to discoveries and ways to ease interfaces despite the deep coupling of the many aspects of a tokamak plant. A power plant’s plasma, materials and components will be in new parameter spaces with new mechanisms and combinations; the design will therefore be based to a significant extent on sophisticated physics and engineering models making substantial extrapolations. There are however gaps in understanding as well as data – together these are termed “uncertainties”. Early integration in depth therefore represents a conceptual, intellectual and practical challenge, a challenge sharpened by the time pressure imposed by the global need for low carbon energy supplies such as fusion. There is an opportunity (and need) to use emerging transformational advances in computational algorithms and hardware to integrate and advance, despite the “uncertainties” and limited experimental data. We use examples to explore how an integrated approach has the potential to lead to consistent designs that could also be resilient to the residual uncertainties. The paper may stimulate some new thinking as fusion moves to the design of complete power plants alongside an evolving and maturing research programme.

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“…Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. lattice defects within tungsten act as strong traps for hydrogen isotopes [7][8][9][10][11][12]. While the modelling of binding energies of hydrogen to prototypical small defects is properly undertaken by density functional calculations, there is an emerging awareness that in the high irradiation dose limit the complex defect microstructure both generates and is responsive to stress [13,14].…”

Section: Introductionmentioning

confidence: 99%

An empirical potential for simulating hydrogen isotope retention in highly irradiated tungsten

Mason,

Nguyen-Manh,

Lindblad

et al. 2023

J. Phys.: Condens. Matter

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We describe the parameterization of a tungsten-hydrogen empirical potential designed for use with large-scale molecular dynamics simulations of highly irradiated tungsten containing hydrogen isotope atoms, and report test results. Particular attention has been paid to getting good elastic properties, including the relaxation volumes of small defect clusters, and to the interaction energy between hydrogen isotopes and typical irradiation-induced defects in tungsten. We conclude that the energy ordering of defects changes with the ratio of H atoms to point defects, indicating that this potential is suitable for exploring mechanisms of trap mutation, including vacancy loop to plate-like void transformations.

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Deuterium retention in W and binary W alloys irradiated with high energy Fe ions

Cited by 18 publications

References 18 publications

Deuterium retention in W-Ta alloys after low-temperature plasma irradiation and gas exposure

Deuterium retention in W-Ta alloys after low-temperature plasma irradiation and gas exposure

Towards a fusion power plant: integration of physics and technology

An empirical potential for simulating hydrogen isotope retention in highly irradiated tungsten

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