Only limited data are available on tritium release from irradiated Be. Few models have been suggested for tritium release from beryllium. Simple diffusion/desorption models have been proposed, but lack the capability of accounting for important phenomena such as burst release through interconnected porosity and the effect of the Be0 impurity layer. This paper describes the application of a new model for tritium release from Be, BETTY, to the analysis of recent experimental data. The model includes diffusion through Be and BeO, surface desorption and diffusion through interconnected porosity (as-fabricated or irradiation-induced). Tritium diffusion and desorption coefficients for Be and Be0 are estimated from the analysis and compared to pre...
A model based on a reaction-diffusion approach is used to simulate thermal desorption experiments pe...
The atomistic understanding of retention and release processes of deuterium in beryllium is reached ...
Study of tritium and helium release from beryllium pebbles with diameters of 0.5 and 1mm after high-...
A tritium transport model called BETTY has been developed to describe and predict the kinetics of tr...
Beryllium will be the first wall material for the international fusion reactor ITER. Due to the heav...
Plasma-facing surfaces of the International Thermonuclear Experimental Reactor (ITER) will take up t...
Tritium depth profile and its temperature programmed desorption rate were determined for selected sa...
Tritium depth profile and its temperature programmed desorption rate were determined for selected sa...
Material mixing effects on erosion/deposition and tritium retention in ITER have been modelled with ...
Tritium behavior in plasma-facing components (PFCs) of future tokamak reactors such as ITER is an es...
Beryllium is proposed to be a neutron multiplier and plasma facing material in future fusion devices...
For deuterium–tritium fusion reactor, the fuel of tritium is not available naturally. Tritium should...
International audienceITER will use beryllium as a plasma-facing material in the main chamber, cover...
Increase of tritium concentration in the primary coolant for the research and testing reactors durin...
L’installation ITER a pour finalité de démontrer la maîtrise de la production d’énergie par fusion t...
A model based on a reaction-diffusion approach is used to simulate thermal desorption experiments pe...
The atomistic understanding of retention and release processes of deuterium in beryllium is reached ...
Study of tritium and helium release from beryllium pebbles with diameters of 0.5 and 1mm after high-...
A tritium transport model called BETTY has been developed to describe and predict the kinetics of tr...
Beryllium will be the first wall material for the international fusion reactor ITER. Due to the heav...
Plasma-facing surfaces of the International Thermonuclear Experimental Reactor (ITER) will take up t...
Tritium depth profile and its temperature programmed desorption rate were determined for selected sa...
Tritium depth profile and its temperature programmed desorption rate were determined for selected sa...
Material mixing effects on erosion/deposition and tritium retention in ITER have been modelled with ...
Tritium behavior in plasma-facing components (PFCs) of future tokamak reactors such as ITER is an es...
Beryllium is proposed to be a neutron multiplier and plasma facing material in future fusion devices...
For deuterium–tritium fusion reactor, the fuel of tritium is not available naturally. Tritium should...
International audienceITER will use beryllium as a plasma-facing material in the main chamber, cover...
Increase of tritium concentration in the primary coolant for the research and testing reactors durin...
L’installation ITER a pour finalité de démontrer la maîtrise de la production d’énergie par fusion t...
A model based on a reaction-diffusion approach is used to simulate thermal desorption experiments pe...
The atomistic understanding of retention and release processes of deuterium in beryllium is reached ...
Study of tritium and helium release from beryllium pebbles with diameters of 0.5 and 1mm after high-...