Sub-surface structures of ITER-grade W (Japan) and re-crystallized W after ITER-similar low-energy and high-flux D plasma loadings

Lindig, S.; Balden, M.; Alimov, V.Kh.; Manhard, A.; Höschen, Carmen; Höschen, T.; Tyburska-Püschel, B.; Roth, J.

doi:10.1088/0031-8949/2011/t145/014039

Cited by 39 publications

(48 citation statements)

References 24 publications

(34 reference statements)

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“…This might be an explanation for the decrease in the low-temperature peak by annealing. On the other hand, vacancies can be generated by the high-flux plasma exposure as a result of plastic deformation due to high mechanical stresses created by the deuterium concentration strongly exceeding the solubility limit [12,15,16]. Dislocations themselves are probably too weak traps to retain deuterium at room temperature, as was discussed above.…”

Section: Discussionmentioning

confidence: 99%

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: Discussionmentioning

confidence: 99%

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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“…It is pertinent to remind that intrinsic intergranular cracks ( temperatures below 500 K, the D retention in the ITER-grade W is higher than that for recrystallized W a) [9,15,21] (Fig. 7).…”

Section: Discussionmentioning

confidence: 99%

“…Near room temperature, i.e. below BDTT, the stress relaxation results in brittle crack formation inside the grains [7,21].…”

Section: Discussionmentioning

confidence: 99%

Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma

Alimov¹,

Tyburska-Püschel²,

Lindig³

et al. 2012

Journal of Nuclear Materials

117

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“…Typically blisters due to D implantation into W occur in this depth range [8,15,20]. It was recently suggested that blisters do not only retain D in form of molecules inside the cavity, but also D atoms in trap sites in the surrounding of the blisters which are created by plastic deformation of the W lattice [8].…”

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confidence: 99%

Influence of nitrogen pre-implantation on deuterium retention in tungsten

et al. 2014

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Abstract:The influence of nitrogen (N) pre-implantation on the deuterium (D) retention in tungsten (W) at different temperatures was investigated. Bulk W samples were exposed to D plasma with a fluence of 110 24 D/m 2 with or without nitrogen pre-implantation at 300 K and 500 K, respectively. Nuclear reaction analysis was applied for the determination of N content and D retention in the near surface. Optical microscopy was used to investigate the surface modification by blistering after implantation. It is shown that, the W:N layers formed during the N preimplantation play very different roles on D retention and blistering in the samples at different temperatures. At 500 K, the W:N layer seems to enhance D diffusion into the bulk by suppressing D loss from the surface, which results in a much higher D concentration in the bulk and larger blisters than without N pre-implantation. At 300 K, the effect of this layer is much less pronounced than that at 500 K.

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Sub-surface structures of ITER-grade W (Japan) and re-crystallized W after ITER-similar low-energy and high-flux D plasma loadings

Abstract: Abstract:Tungsten is a promising candidate for plasma facing materials in fusion reactors.

Cited by 39 publications

References 24 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

Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma

Influence of nitrogen pre-implantation on deuterium retention in tungsten

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