The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern to the fusion community as the scale of tritium retention by this mechanism could be a limiting factor for the operation of fusion reactors, such as ITER. Hence there is a need to investigate ways of mitigating T retention and also for detritiating surfaces by either desorption of T or removal of tritiated deposits. The results of the removal of codeposits from CFC tiles by pulsed laser ablation are reported here. The results show that it is possible to completely remove a 300μm thick hydrogen isotope rich carbon film at a rate of 12x10-3m2/hr by this method and that with optimisation of the laser parameters there is scope to improve the treat...
Samples of a limiter tile from the TEXTOR tokamak were investigated by scanning electron microscopy ...
Accelerator mass spectrometry (AMS) and the full combustion method (FCM) followed by liquid scintill...
The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been meas...
The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern t...
A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbo...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
International audienceTreatments of plasma facing components (PFCs) are major issues for ITER operat...
Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing...
ITER operation might be limited by the tritium inventory that will be retained in carbon tiles and r...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Next generation tokamaks offer the possibility of highly efficient energy generation from the fusion...
Tritium in first wall materials of fusion machines is a matter of concern not only for inventory pur...
Tritium issues will play a central role in the performance and operation of next-step deuterium-trit...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
Next generation tokamaks offer the possibility of highly efficient energy generation from the fusion...
Samples of a limiter tile from the TEXTOR tokamak were investigated by scanning electron microscopy ...
Accelerator mass spectrometry (AMS) and the full combustion method (FCM) followed by liquid scintill...
The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been meas...
The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern t...
A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbo...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
International audienceTreatments of plasma facing components (PFCs) are major issues for ITER operat...
Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing...
ITER operation might be limited by the tritium inventory that will be retained in carbon tiles and r...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Next generation tokamaks offer the possibility of highly efficient energy generation from the fusion...
Tritium in first wall materials of fusion machines is a matter of concern not only for inventory pur...
Tritium issues will play a central role in the performance and operation of next-step deuterium-trit...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
Next generation tokamaks offer the possibility of highly efficient energy generation from the fusion...
Samples of a limiter tile from the TEXTOR tokamak were investigated by scanning electron microscopy ...
Accelerator mass spectrometry (AMS) and the full combustion method (FCM) followed by liquid scintill...
The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been meas...