Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped divertor region in JT-60U
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference38 articles.
1. Hydrogen isotope inventory in the graphite divertor tiles of ASDEX Upgrade as measured by thermal desorption spectroscopy
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3. Tritium retention of plasma facing components in tokamaks
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5. The effect of UV light irradiation on the removal of tritium from the codeposited carbon–tritium layer in fusion reactors
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2. A review of the LIBS analysis for the plasma-facing components diagnostics;Journal of Nuclear Materials;2020-12
3. Review of LIBS application in nuclear fusion technology;Frontiers of Physics;2016-09-18
4. Ion irradiation of 37Cl implanted nuclear graphite: Effect of the energy deposition on the chlorine behavior and consequences for the mobility of 36Cl in irradiated graphite;Journal of Nuclear Materials;2015-09
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