首页|The erosion and retention properties of tungsten trioxide films exposed to low energy deuterium ions: Temperature dependence

The erosion and retention properties of tungsten trioxide films exposed to low energy deuterium ions: Temperature dependence

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The erosion behavior and retention properties of tungsten trioxide (WO3) and W films exposed to low energy (~50 eV) deuterium (D) ions were studied at surface temperature from 403 K to 758 K. The initial thickness of WO3 and W films are approximately 7.0 x 10(18) atoms cm(-2) and 1.8 x 10(18) atoms cm(-2), respectively. The erosion rate of oxygen (O) by deuterium is thermally enhanced, and tungsten (W) atoms can be sputtered rapidly in the form of WxOy molecules and/or W atoms at higher temperatures due to the relatively weak binding energy between W and O, resulting on an increase in the W sputtering yield with temperature. Nano-sized pinholes appear on the surface at 403 K, however, pinholes with much smaller sizes and cracks appear on the surface at higher temperatures, and their density increases with increasing temperatures. The synergistic effects of ion irradiation and temperature cause the structure change of tungsten oxide films according to Raman spectra. X-ray photoelectron spectroscopy shows that after irradiation with D ions, metallic W appears on the surface, but the tungsten oxide is still present. Trapped D is almost uniformly distributed in WO3 and its concentration is much higher than that in W at lower irradiation temperature, which is mainly related to D atoms chemically bonded to O atoms with the formation of deuterium tungsten bronze. The thermal desorption peak temperatures of D-2 (~465 K or 500 K) and D2O (~495 K, 730 K (or 790 K) and 825 K) are related to the heating rate (1 K s(-1)) and it implies that the deuterium tungsten bronze is decomposed under the low D ion irradiation temperatures. (C) 2022 Elsevier B.V. All rights reserved.

Tungsten trioxideDeuterium ion irradiationChemical erosionTungsten enrichmentTemperature dependenceOXIDEREDUCTIONENHANCEMENTBERYLLIUMCARBONLAYERS

Tu, Hanjun、Li, Cong、Ding, Wei、Shi, Liqun、Zhang, Youpeng

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Fudan Univ

China Acad Engn Phys

2022

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN:0022-3115
年,卷(期):2022.562
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