Deuterium retention in tungsten for fusion use

Haasz, A.A.; Davis, J.W.; Poon, M.C.; Macaulay-Newcombe, R.G.

doi:10.1016/s0022-3115(98)00072-5

Cited by 120 publications

(90 citation statements)

References 6 publications

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“…Enhanced retention in pre-exposed samples has been observed before [13,14]. However, there exists a significant difference between the presented data and the ones available from the literature.…”

Section: Discussioncontrasting

confidence: 62%

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Zayachuk¹,

Hoen²,

Emmichoven³

et al. 2012

Nucl. Fusion

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A direct comparison of deuterium retention in samples of tungsten and two grades of tungsten-tantalum alloys-W1%Ta and W-5%Ta, exposed to deuterium plasmas (ion flux ∼10 24 m −2 s −1 , ion energy at the biased target ∼50 eV) at the plasma generator Pilot-PSI was performed using thermal desorption spectroscopy (TDS). No systematic difference in terms of total retention in tungsten and tungsten-tantalum was identified. The measured retention value for each grade did not deviate by more than 24% from the value averaged over the three grades exposed to the same conditions. No additional desorption peaks appeared in the TDS spectra of the W-Ta samples as compared with the W target, indicating that no additional kinds of traps are introduced by the alloying of W with Ta. In the course of the experiment the same samples were exposed to the same plasma conditions several times, and it is demonstrated that samples with the history of prior exposures yield an increase in deuterium retention of up to 130% under the investigated conditions compared with the samples that were not exposed before. We consider this as evidence that exposure of the considered materials to ions with energy below the displacement threshold generates additional traps for deuterium. The positions of the release peaks caused by these traps are similar for W and W-Ta, which indicates that the corresponding traps are of the same kind.

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Section: Discussioncontrasting

confidence: 62%

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Zayachuk¹,

Hoen²,

Emmichoven³

et al. 2012

Nucl. Fusion

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“…3 a). In the polycrystalline W exposed to the "clean" D plasma, the D retention demonstrates practically the same temperature dependence as that in the W single crystal, but the maximum retention in the polycrystalline W is about 5×10 20 D/m 2 at T exp = 493 K (Fig. 3 a).…”

Section: Deuterium Depth Profilesmentioning

confidence: 81%

“…The dominant factors influencing the hydrogen isotope retention in plasma exposed tungsten were the substrate temperature, T exp , and whether carbon was deposited on the tungsten surface. For uncontaminated tungsten surfaces the total isotope retention at T exp ≤ 500 K was in the range from about 5×10 20 to about 5×10 21 D/m 2 . These values were about one order of the magnitude higher than those after exposure at higher temperatures (>700 K).…”

Section: Introductionmentioning

confidence: 95%

Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmas

Alimov¹,

Roth²,

Causey³

et al. 2008

Journal of Nuclear Materials

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“…Deuterium implanted at T = 500 K diffuses through tungsten and enters aluminum layer from the coating-free side of the sample. Deuterium can diffuse through tungsten for large distances (≈ 0.1 mm) at T = 500K [8]. TDS analysis of the spectra in Figure 1, we can conclude that approx.…”

Section: Resultsmentioning

confidence: 71%

Deuterium diffusion and retention in tungsten coated with barrier layer during ion irradiation

Begrambekov

Kaplevsky

Dovganyuk

et al. 2017

J. Phys.: Conf. Ser.

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Abstract.The results of the comparative analysis of low-temperature desorption of deuterium from tungsten coated with aluminum and yttrium films under the irradiation by hydrogen plasma with oxygen impurity are presented. The irradiation of aluminum or yttrium coating by H 2 +1%O 2 plasma leads to the desorption of implanted deuterium from the samples. It was shown that the number of atoms desorbed depends on the sign of enthalpy of hydrogen solution in the metal film. IntroductionBeryllium and tungsten are chosen as the materials for the first wall and the diverter of the ITER tokamak, respectively. Beryllium and tungsten have oxide layers formed on their surfaces. It is known that the oxide layers function as barriers for hydrogen diffusion. The surface of tungsten and beryllium will be coated by oxides if the ITER plasma would have an oxygen impurity. Sputtered beryllium atoms will be deposited on the surfaces of tungsten tiles and form oxide layers under these conditions. The research on the influence of beryllium films on hydrogen isotope trapping and desorption from tungsten is of interest from the safety perspective as the limit for the accumulation of tritium in the walls cannot be exceeded.The authors of paper [1] have discovered the effect of low-temperature hydrogen isotope desorption from stainless steel at T ≈ 320 K under the irradiation by hydrogen ions in hydrogen atmosphere with oxygen impurity, as well as hydrogen plasma with oxygen impurity. This effect is explained by the processes initiated by inelastic collisions of deuterium and oxygen atoms/ions with the chromium oxide layer on the surface of stainless steel [2]. Trapping and retention of hydrogen in stainless steel and tungsten with oxide layers were studied in several works [3][4][5]. However, the influence of surface oxide layers on hydrogen trapping and desorption from metal during ion irradiation has not been properly investigated as of today.In this work, a comparative research on the effect of low temperature desorption of hydrogen isotopes from tungsten samples with surface barrier coatings like aluminum, which is considered as a proxy for beryllium in laboratory experiments, and yttrium with oxidized surfaces. The task was to identify the characteristics of the process in cases when the metal (tungsten) and the barrier layer (aluminum) are metals with positive enthalpy of hydrogen solution (+1.1 eV/at [6] and +0.7 eV/at [6], respectively), and in case when the enthalpy of hydrogen solution in the barrier layer (yttrium) is negative (-0.85 eV/at [6]).

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Deuterium retention in tungsten for fusion use

Cited by 120 publications

References 6 publications

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmas

Deuterium diffusion and retention in tungsten coated with barrier layer during ion irradiation

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