4.5 Article

Evolution of Defects in CVD-W Irradiated by H/He Neutral Beam Using Positron Annihilation Spectroscopy

Journal

METALS
Volume 11, Issue 2, Pages -

Publisher

MDPI
DOI: 10.3390/met11020211

Keywords

CVD-W; H/He; DB-SPBA

Funding

  1. Nation Natural Science Foundation of China [.11675114]

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The study focused on the performance of CVD-W under different neutral beam irradiation conditions, showing a decrease in vacancy-type defect concentration at higher temperatures and complex defect types under H + 6 at.% He irradiation.
One of the key problems for the application of nuclear fusion energy is to select the suitable plasma facing materials (PFMs). Among the W-based materials, CVD-W exhibits some unique advantages. In order to estimate the performance of CVD-W under the fusion environment, the vacancy-type defects and their evolution are investigated by the Doppler-broadening slow positron beam analysis (DB-SPBA) combined with SEM (scanning electron microscope). There are two kinds of neutral beam irradiation, the pure H neutral beam and the H + 6 at.% He neutral beam irradiation, which are performed at the neutral beam facility GLADIS (IPP, Germany). The surface temperatures of CVD-W irradiated by H (H + 6 at.% He) are 850 and 1000 (700 and 800 degrees C). By comparing the samples under different conditions, the defect evolution of CVD-W is obtained. As for the pure H neutral beam irradiated samples, the DB-SPBA results demonstrate that the CVD-W sample at the surface temperature of 1000 degrees C, compared to the 850 degrees C sample, shows a decrease in S parameters, which is due to the reduction of vacancy-type defect concentration. The defect damage layer in 1000 degrees C sample is narrower than that of 850 degrees C sample and the defect type tends to be consistent in 1000 degrees C sample. The SEM results suggest that the surface damage of the 1000 degrees C sample was recovered to some extent. As for the H + 6 at.% He neutral beam irradiated samples, compared with the CVD-W sample at the surface temperature of 700 degrees C, the 800 degrees C sample shows an increased S parameters, which can be attributed to the volume increase of vacancy-type defect. The defect damage layer in the 800 degrees C sample is wider than that of the 700 degrees C sample. Both the H + 6 at.% He irradiated samples show complex defect types. The surface of the 800 degrees C sample exhibits more dense pinhole damage structures compared to that of the 700 degrees C sample.

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