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Development of fibered LIBS device for tokamak Plasma Facing Components characterization
The LIBS technique enables to measure the deposits composition in fusion machines, particularly the tritium concentration on tokamak Plasma Facing Components (PFC), thus allowing the estimation of the deposited tritium quantity for safety control and the composition of the PFC surface in light impur...
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Published in: | Fusion engineering and design 2023-12, Vol.197, p.114077, Article 114077 |
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Main Authors: | , , , , , , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
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Summary: | The LIBS technique enables to measure the deposits composition in fusion machines, particularly the tritium concentration on tokamak Plasma Facing Components (PFC), thus allowing the estimation of the deposited tritium quantity for safety control and the composition of the PFC surface in light impurities (oxides) which can pollute the plasma when evaporated. This paper presents the development of a fibered LIBS device, mounted on an articulated arm and able to operate in nanosecond and picosecond laser regimes for PFC characterizations. The different components of the LIBS device are presented as well as the first LIBS spectra on tungsten targets. |
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ISSN: | 0920-3796 |
DOI: | 10.1016/j.fusengdes.2023.114077 |