AbstractRetention and desorption of hydrogenic species need to be accurately modeled to predict the tritium inventory of next generation fusion devices, which is needed both for tritium fuel recovery and for tritium safety concerns. In this paper, experiments on thermal desorption of deuterium from intrinsic polycrystalline tungsten defects using laser heating are compared to TMAP-7 modeling. The samples during deuterium plasma exposure were at a temperature of 373K for this benchmark study with ion fluence of 0.7–1.0 ×1024Dm−2. Following plasma exposure, a fiber laser (λ= 1100nm) heated the samples to peak surface temperatures ranging from ∼500 to 1400K with pulse widths from 10ms to 1s, and 1 to 10 pulses applied to each sample. The remai...
The possible mutual influence and synergistic effect between defect production and the presence of h...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
A fundamental obstacle to controlled fusion devices is the retention of hydrogenic fuel in Plasma Fa...
AbstractRetention and desorption of hydrogenic species need to be accurately modeled to predict the ...
Retention and desorption of hydrogenic species need to be accurately modeled to predict the tritium ...
AbstractTo investigate the synergistic effects of fuel retention in tungsten, experiments were perfo...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-I...
Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads fro...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
AbstractIn the present work hydrogen isotopes exchange in recrystallized tungsten was investigated a...
The possible mutual influence and synergistic effect between defect production and the presence of h...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
A fundamental obstacle to controlled fusion devices is the retention of hydrogenic fuel in Plasma Fa...
AbstractRetention and desorption of hydrogenic species need to be accurately modeled to predict the ...
Retention and desorption of hydrogenic species need to be accurately modeled to predict the tritium ...
AbstractTo investigate the synergistic effects of fuel retention in tungsten, experiments were perfo...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
Development of methods to characterise the first wall in ITER and future fusion devices without remo...
We investigated the effect of surface temperature on deuterium retention in self-damaged tungsten ex...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
Tungsten is a candidate plasma facing material for next generation magnetic fusion devices such as ...
For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-I...
Leading edges of the ITER tungsten (W) divertor are expected to melt due to transient heat loads fro...
AbstractInteraction of deuterium with radiation defects in tungsten was studied by means of thermal ...
AbstractIn the present work hydrogen isotopes exchange in recrystallized tungsten was investigated a...
The possible mutual influence and synergistic effect between defect production and the presence of h...
AbstractThermal desorption spectroscopy (TDS) of tungsten implanted with D2+ ions was performed afte...
A fundamental obstacle to controlled fusion devices is the retention of hydrogenic fuel in Plasma Fa...