Tritium retention in the plasma facing components and co-deposition in re-deposited layers is a key issue for ITER, since the operation of the machine will be restricted to a maximum inventory of tritium. Development of methods to detect in real time the amount of retained fuel in the in vessel components is urgently required. A promising method for this is the pulsed laser induced desorption, by which the imbedded gas in such layers is released into the plasma where the injected atoms and molecules are excited and ionised and the characteristic line emission is detected spectroscopically. In this paper the release process is investigated in detail for amorphous hydrocarbon layers in a laboratory experiment, as a prerequisite for the later ...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
An experimental set-up and spectroscopy diagnostic method for laser-induced fuel removal and decompo...
19th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Uni...
ITER operation might be limited by the tritium inventory that will be retained in carbon tiles and r...
The use of carbon for plasma-facing components in ITER is assumed to cause the safety limit of a max...
Long term tritium retention is one of the most critical issues for ITER and future fusion devices. W...
International audienceTreatments of plasma facing components (PFCs) are major issues for ITER operat...
Measurement and control of long term tritium retention is one of the most critical issues for ITER a...
Laser-based techniques in combination with spectroscopy are proposed for in situ characterization of...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
In situ methods to measure the fuel retention and to characterize the material deposition on the wal...
Plasma-facing components (PFCs) at ITER are eroded and the material is transported by the edge plasm...
For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-I...
International audienceIn this paper, in situ tritium measurements and control by laser techniques ar...
Laser Induced Desorption Spectroscopy (LIDS) is a diagnostic method to measure the hydrogen content ...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
An experimental set-up and spectroscopy diagnostic method for laser-induced fuel removal and decompo...
19th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Uni...
ITER operation might be limited by the tritium inventory that will be retained in carbon tiles and r...
The use of carbon for plasma-facing components in ITER is assumed to cause the safety limit of a max...
Long term tritium retention is one of the most critical issues for ITER and future fusion devices. W...
International audienceTreatments of plasma facing components (PFCs) are major issues for ITER operat...
Measurement and control of long term tritium retention is one of the most critical issues for ITER a...
Laser-based techniques in combination with spectroscopy are proposed for in situ characterization of...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
In situ methods to measure the fuel retention and to characterize the material deposition on the wal...
Plasma-facing components (PFCs) at ITER are eroded and the material is transported by the edge plasm...
For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-I...
International audienceIn this paper, in situ tritium measurements and control by laser techniques ar...
Laser Induced Desorption Spectroscopy (LIDS) is a diagnostic method to measure the hydrogen content ...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
An experimental set-up and spectroscopy diagnostic method for laser-induced fuel removal and decompo...
19th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), Uni...