Within the framework of the R&D activities promoted by European Fusion Development Agreement on the helium-cooled pebble bed test blanket module to be irradiated in ITER, ENEA Brasimone and the Department of Nuclear Engineering of the University of Palermo performed intense research activities on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramics pebble beds, which are envisaged to be used, respectively, as neutron multiplier and tritium breeder. In particular, at the DIN a thermo mechanical constitutive model was developed for both lithiated ceramics and beryllium pebble beds and it was successfully implemented on a commercial finite element code to analyze the experimental results of the ENEA test ca...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
Zur Beschreibung der thermomechanischen Wechselwirkung zwischen keramischen Brutmaterial- und Beryll...
This paper illustrates a neutronic and thermal analysis of an hypothetical triziogen blanket for ITE...
Within the framework of the R&D activities promoted by European Fusion Development Agreement on the ...
Within the framework of the R&D activities promoted by European Fusion Development Agreement on the ...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
The helium cooled pebble bed (HCPB) Test blanket module (TBM) for the DEMO Reactor foresees the util...
The Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) to be tested in ITER (International Th...
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
Several blanket designs based on lithium ceramic and Beryllium pebble beds are currently considered ...
The thesis analyzes the thermo-mechanical behavior of the Breeder Unit (BU). The BU is a component o...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
Packed pebble beds are particular granular systems composed of a large amount of small particles, ar...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
Zur Beschreibung der thermomechanischen Wechselwirkung zwischen keramischen Brutmaterial- und Beryll...
This paper illustrates a neutronic and thermal analysis of an hypothetical triziogen blanket for ITE...
Within the framework of the R&D activities promoted by European Fusion Development Agreement on the ...
Within the framework of the R&D activities promoted by European Fusion Development Agreement on the ...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
The helium cooled pebble bed (HCPB) Test blanket module (TBM) for the DEMO Reactor foresees the util...
The Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) to be tested in ITER (International Th...
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
Several blanket designs based on lithium ceramic and Beryllium pebble beds are currently considered ...
The thesis analyzes the thermo-mechanical behavior of the Breeder Unit (BU). The BU is a component o...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
Packed pebble beds are particular granular systems composed of a large amount of small particles, ar...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
Zur Beschreibung der thermomechanischen Wechselwirkung zwischen keramischen Brutmaterial- und Beryll...
This paper illustrates a neutronic and thermal analysis of an hypothetical triziogen blanket for ITE...