Deuterium permeation in tungsten by mixed ion irradiation

Ueda, Y.; Lee, H.T.; Peng, Hong Yan; Ohtsuka, Y.

doi:10.1016/j.fusengdes.2012.03.006

Cited by 14 publications

(10 citation statements)

References 34 publications

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“…The simulation results also showed that the vacancy-like defects could be the possible trapping sites for hydrogen isotopes [22]. These facts were consistent with the previous report by Y. Ueda that the damages did not largely affect the hydrogen permeation behavior in W [23].…”

Section: Journal Of Nuclear Science and Technologysupporting

confidence: 91%

Deuterium permeation behavior for damaged tungsten by ion implantation

Oya

Sato

et al. 2015

Journal of Nuclear Science and Technology

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The deuterium (D) permeation behaviors for ion-damaged tungsten (W) by 3 keV D 2 + and 10 keV C + were studied. The D permeability was obtained for un-damaged W at various temperatures. For both D 2 + and C + implanted W, the permeability was clearly reduced. But, for the D 2 + implanted W, the permeability was recovered by heating at 1173 K and it was almost consistent with that for un-damaged W. In the case of C + implanted W, the permeability was not recovered even if the sample was heated at 1173 K, indicating that the existence of carbon would prevent the recovery of permeation path in W. In addition, transmission electron microscope (TEM) observation showed the voids were grown by heating at 1173 K and not removed, showing the existence of damages would not largely influence on the hydrogen permeation behavior in W in the present study.

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Section: Journal Of Nuclear Science and Technologysupporting

confidence: 91%

Deuterium permeation behavior for damaged tungsten by ion implantation

Oya

Sato

et al. 2015

Journal of Nuclear Science and Technology

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“…4 To verify this hypothesis, we performed the same measurements at 873 K using a specimen that had been previously heated to 1173 K. For both the permeability and diffusion coefficient, this reduced the difference between the irradiated and un-damaged W by more than 50%. The permeability for 3.0 keV D 2 + implanted into W was also reduced [15], but eventually reached the same value that was measured for un-damaged W as the sample was heated up to 1173 K [13]. Taking these results into consideration, it is possible that He bubbles worked as a diffusion barrier at higher temperatures (e.g.…”

Section: Experimental Configurationsupporting

confidence: 67%

“…Prior temperature-programmed desorption and depth profiling measurements indicate that deuterium (D) diffusion into the W bulk is reduced considerably as a result of mixed species irradiation. The prevailing hypothesis is that the dense layer of He bubbles formed near the W surface [12][13] strongly influences this migration.…”

Section: Introductionmentioning

confidence: 99%

Effect of helium irradiation on deuterium permeation behavior in tungsten

Uemura

Sakurada

Fujita

et al. 2017

Journal of Nuclear Materials

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In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He +). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He + was approximately one order of magnitude lower than that for undamaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for undamaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability and diffusion coefficients return to levels observed for undamaged material. It is possible that these effects are linked to annealing of defects introduced by ion damage, and whether the defects are stabilized by the presence of trapped He.

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“…Much recent efforts have been devoted to understanding the interaction of H with W between experiment [3][4][5][6][7] and simulation [8][9][10][11][12][13][14][15][16][17][18][19]. We know that the implanted H ions can easily diffuse into the inner of metal and they will eventually find the suitable trapping sites and collect [20,21], leading to the nucleation and growth of H blistering [22,23].…”

Section: Introductionmentioning

confidence: 99%

“…We know that the implanted H ions can easily diffuse into the inner of metal and they will eventually find the suitable trapping sites and collect [20,21], leading to the nucleation and growth of H blistering [22,23]. Experiments have shown that the bombardment of high flux of H isotope ions on W material [4,5,23] can cause roughening and blistering in W. Accordingly, H blistering accumulation will change the microstructures and mechanical properties of W, which is the most important issue in developing W as a PFM. In our previous study [9], we reveal a microscopic vacancy trapping mechanism for H blistering formation in bulk W based on firstprinciples investigations of the energetics of H-vacancy interaction and the kinetics of H diffusion.…”

Section: Introductionmentioning

confidence: 99%