Void growth and thermal desorption of deuterium from voids in tungsten

Eleveld, H.; Veen, A. van

doi:10.1016/0022-3115(94)91062-6

Cited by 114 publications

(93 citation statements)

References 11 publications

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“…Exposure conditions for each exposure of each sample are summarized in table 1. The temperature during exposure ensured that vacancies were not mobile (in W, vacancies become mobile at 550-600 K [7,8]). …”

Section: Methodsmentioning

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: Methodsmentioning

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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“…Due to the small difference in the trapping energy of a deuterium atom trapped in a vacancy and the trapping energy of deuterium molecules in microvoids or microcavities [13][14][15][16], it may be difficult to resolve these two trap sites experimentally. On the other hand, TDS measurements influence the initial D distribution by annealing.…”

Section: Modelingmentioning

confidence: 99%

“…Moreover, calculations with only intrinsic defects do not describe the experimental depth profiles at all as one can see from Thus, the density of voids is less than vacancies. Since, at such a low temperature as 400 K the vacancies in W are still immobile [13], the formation of voids at 400 K is due to the stress field induced by energetic ions. This means that the stress-induced field results in an agglomeration of vacancies in voids and a production of dislocations during implantation even at such a low temperature as 400 K. The reduction of the bubble density with increasing ion energy was also observed by Sakamoto et al [24].…”

Section: Peculiarity At Low-energy Implantation: Nature Of Low-energymentioning

confidence: 99%

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Ion-driven deuterium retention in tungsten

Огородникова

Roth

Mayer

2008

Journal of Applied Physics

210

153

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“…H retention is expressed in surface modification, formation of subsurface blisters and accumulation of H in the bulk material. These effects are attributed to trapping of H atoms on lattice defects such as vacancies, dislocations/grain boundaries and voids [2][3][4]. Typical kinetic energy of H ions coming from plasma (below 500 eV ) is far below the threshold energy needed to create a stable Frenkel-pair defect in W, and the implantation range of H ions is limited to several nanometers [5].…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis of TDS spectra under high and low flux plasma exposure conditions

et al. 2016

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Recently developed numerical model, based on the dislocation-driven nucleation of gas bubbles, is used to analyse experimental results on deuterium retention in tungsten under ITER relevant plasma exposure conditions. Focus is put on understanding the relation between exposure temperature and flux on primary features of thermal desorption spectra: peak positions and intensities of the desorption flux. The model allows one to relate the peak positions with the size of plasma induced deuterium bubbles and envisage exposure conditions (temperature and flux) for their formation. Based on the performed analysis, dedicated experimental conditions to validate the model are proposed.

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Void growth and thermal desorption of deuterium from voids in tungsten

Cited by 114 publications

References 11 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

Ion-driven deuterium retention in tungsten

Numerical analysis of TDS spectra under high and low flux plasma exposure conditions

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