Deuterium plasma exposure of thin oxide films on tungsten-oxygen removal and deuterium uptake

被引:3
作者
Kremer, Kristof [1 ,2 ]
Schwarz-Selinger, Thomas [1 ]
Jacob, Wolfgang [1 ]
机构
[1] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[2] Tech Univ Munich, Phys Dept E28, D-85747 Garching, Germany
关键词
Tungsten; Tungsten oxide; Permeation barrier; Hydrogen uptake; Hydrogen retention; Plasma irradiation; Ion -damaged tungsten; Deuterium uptake; Deuterium retention; Nuclear fusion; NUCLEAR-REACTION;
D O I
10.1016/j.nme.2023.101406
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Recently we have shown that thin (33 to 55 nm) oxide films on tungsten (W) prevent deuterium (D) uptake from a low-temperature plasma (5 eV/D; 370 K; 1.4 x 1024 D/m2) into metallic W. Here we continue this investigation with higher D fluence up to 2.3 x 1025 D/m2 and, additionally, with higher D energies up to 38 eV/D or a higher sample temperature of 500 K. We investigate the reduction mechanism of the oxide and determine under which conditions the permeation barrier effect for D breaks down. We show that during prolonged plasma exposure at 5 eV/D and 370 K, the W-enriched zone that forms at the surface of the oxide stops growing and continues to protect the oxide beneath it against further reduction. For a fluence of 1.6 x 1025 D/m2, an originally 55 nm thick oxide film reduces D uptake into the metal by 99 %. D enters the metal solely by small cracks in the oxide that form during reduction by the plasma. For higher temperature or D energies, the reduction becomes stronger and more inhomogeneous. D uptake into the metal increases proportional to the area of oxide/metal interface on which the oxide is reduced. The new experiments confirm our previous assumption that D uptake into W is blocked due to the difference in enthalpy of solution of D in W oxide and metallic W. D can only enter the metal once the oxide at the interface is sufficiently reduced. Based on the obtained oxide reduction rates, we made a first tentative estimate of the relevance of naturally occurring W oxide films for D uptake in the plasma-facing components of a fusion reactor. We found that the natural oxide will have none or only a very minor effect in this case.
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页数:14
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