2017
DOI: 10.1016/j.fusengdes.2016.10.011
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Hydrogen retention studies on lithiated tungsten exposed to glow discharge plasmas under varying lithiation environments using Thermal Desorption Spectroscopy and mass spectrometry

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Cited by 2 publications
(5 citation statements)
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“…A maximum temperature of 570 °C was reached on the sample surface. Two clear peaks are visible in the TDS spectrum, the first and bigger one at 500 °C of surface temperature and the second one (smaller) at 550 °C, being these results in agreement with previous findings in TDS experiments performed on W-Li films [14]. Assuming that water, hydrogen and other impurity contributions are negligible, the deuterium retention resulted in 1.3 • 10 18 cm −2 , value that agrees reasonably with the LID results (2.0 • 10 18 cm −2 ), being them comparable.…”
Section: Post Mortem Analysis For W-li-d Film Characterizationsupporting
confidence: 92%
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“…A maximum temperature of 570 °C was reached on the sample surface. Two clear peaks are visible in the TDS spectrum, the first and bigger one at 500 °C of surface temperature and the second one (smaller) at 550 °C, being these results in agreement with previous findings in TDS experiments performed on W-Li films [14]. Assuming that water, hydrogen and other impurity contributions are negligible, the deuterium retention resulted in 1.3 • 10 18 cm −2 , value that agrees reasonably with the LID results (2.0 • 10 18 cm −2 ), being them comparable.…”
Section: Post Mortem Analysis For W-li-d Film Characterizationsupporting
confidence: 92%
“…Even for the deepest point (100 µm) situated at the farthest distance from the laser beam incidence, the temperature rose up to 600 °C. Several experimental results have shown that the hydrogenic desorption from lithium is completed at these temperatures [12][13][14]. Consequently, these calculations indicated that the laser shot would be able to heat the sample and induce the total hydrogenic desorption.…”
Section: Irradiation Of W-li-d Samples With the Nd:yag Laser Beammentioning
confidence: 95%
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“…Higher energies however are to be expected near the FW of a reactor, their value given by the ion temperature and sheath potential. In a previous work [20] performed in a GD plasma, it was found that for Li ion energies of several hundred eVs no D retention associated to Li ion bombardment took place as expected from the very low range of implantation of Li on W. Based on these facts, it seems very unlikely that D retention of the FW of a reactor at typical temperatures equal or higher than those used here becomes an issue, as it was found for carbon-based divertor materials.…”
Section: Discussionmentioning
confidence: 90%