Measurement of uptake and release of tritium by tungsten
- Hydrogen Isotope Research Center, University of Toyama, Toyama-shi (Japan)
- Tritium Technology Group, JAEA, Tokai-mura, Naka-gun (Japan)
- Institute for Material Research, Tohoku University, Oarai-machi, Higashiibaraki-gun (Japan)
Tungsten is currently contemplated as plasma facing material for the divertor of future fusion machines. In this paper the uptake of tritium by tungsten and its release behavior have been investigated. Tungsten samples have been annealed at various temperatures and loaded at also different temperatures with deuterium containing 7.2 % tritium at a pressure of 1.2 kPa. A specific system was designed to assess the release of tritiated water and molecular tritium by the samples. Due to the rather low solubility of hydrogen isotopes in tungsten it is particularly important to be aware of the presence of hydrogen traps or thin oxide films. As shown in this work, traps or oxide films may affect the retention capability of tungsten and lead to significantly modified release properties. It became clear that there were capture sites that had different thermal stability and different capture intensity in tungsten after polishing, or oxide films that were grown on the surface of tungsten and had barrier effects.
- OSTI ID:
- 22429752
- Journal Information:
- Fusion Science and Technology, Vol. 67, Issue 3; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 12 refs.; ISSN 1536-1055
- Country of Publication:
- United States
- Language:
- English
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