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.
引用
收藏
页数:14
相关论文
共 50 条
  • [31] Surface modification and deuterium retention of tungsten and tungsten-rhenium alloys exposed to deuterium plasma
    Zhang, Xuexi
    Qiao, Li
    Zhang, Hong
    Yao, Weizhi
    He, Wenhao
    Li, Yuhong
    Wang, Peng
    NUCLEAR MATERIALS AND ENERGY, 2021, 29
  • [32] Surface Topography and Deuterium Retention of Polycrystalline Tungsten and Nanocrystalline Tungsten Film Exposed to Deuterium Plasma
    Yu, Jiangang
    Han, Wenjia
    Lian, Ziwei
    Zhu, Kaigui
    FUSION SCIENCE AND TECHNOLOGY, 2018, 73 (01) : 5 - 12
  • [33] Simulation of Experimental Deuterium Retention in Tungsten under Periodic Deuterium Plasma Irradiation
    Oya, Makoto
    Hara, Yuki
    Katayama, Kazunari
    Ohya, Kaoru
    PLASMA AND FUSION RESEARCH, 2021, 16
  • [34] Microstructure and Deuterium Retention of Tungsten Deposited by Hollow Cathode Discharge in Deuterium Plasma
    孙忠超
    连紫薇
    乔伟娜
    俞坚钢
    韩文佳
    傅青伟
    朱开贵
    Chinese Physics Letters, 2017, 34 (12) : 55 - 59
  • [35] Simulation of Experimental Deuterium Retention in Tungsten under Periodic Deuterium Plasma Irradiation*)
    Oya M.
    Hara Y.
    Katayama K.
    Ohya K.
    Plasma and Fusion Research, 2021, 16 : 2405057 - 1
  • [36] Microstructure and Deuterium Retention of Tungsten Deposited by Hollow Cathode Discharge in Deuterium Plasma
    Sun, Zhong-Chao
    Lian, Zi-Wei
    Qiao, Wei-Na
    Yu, Jian-Gang
    Han, Wen-Jia
    Fu, Qing-Wei
    Zhu, Kai-Gui
    CHINESE PHYSICS LETTERS, 2017, 34 (12)
  • [37] Formation of D inventories and structural modifications by deuterium bombardment of tungsten thin films
    Bizyukov, I
    Krieger, K
    Azarenkov, N
    Levchuk, S
    Linsmeier, C
    JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) : 965 - 969
  • [38] Effects of deuterium plasma exposure and helium ions irradiation on nanoindentation hardness of tungsten
    Zhang, Hong
    Zhang, Xuexi
    Li, Yuhong
    Wang, Peng
    Qiao, Li
    NUCLEAR MATERIALS AND ENERGY, 2024, 40
  • [39] Erosion and deuterium retention in ion-irradiated tungsten under plasma exposure
    Khripunov, B.
    Gureev, V.
    Koidan, V.
    Kornienko, S.
    Latushkin, S.
    Petrov, V.
    Ryazanov, A.
    Semenov, E.
    Stolyarova, V.
    Danelyan, L.
    Kulikauskas, V.
    Zatekin, V.
    Unezhev, V.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 463 : 258 - 262
  • [40] Retention, sputtering and surface chemistry at tungsten oxide surface facing deuterium plasma
    Sharkass, Meral
    Dwivedi, Swarit
    Shin, Yun Kyung
    Nieto-Perez, Martin
    van Duin, Adri C. T.
    Krstic, Predrag S.
    JOURNAL OF NUCLEAR MATERIALS, 2025, 606