Several blanket designs based on lithium ceramic and Beryllium pebble beds are currently considered for fusion reactors. The engineering lay-out of these designs can only be confidently done if models are developed that predict the thermal and mechanical behavior of the pebble beds under fusion boundary conditions, in particular because it is impossible to create a large set of in-pile experimental data reflecting such conditions. Modelling of the pebble bed is complicated by the fact that there is a large number of parameters to be considered. The present report gives an account of the parameters determining the thermomechanical pebble bed behavior. It describes the current status of modelling and experiments used to develop models. On thi...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
This paper is aimed at the evaluation of the thermal conductivity of ceramic pebble beds which are o...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
The thermal stress on breeding blanket structure is one of the main design driver; consequently, an ...
Among the international fusion solid breeder blanket community, there exists steady progress on the ...
Among the international fusion solid breeder blanket community, there exists steady progress on the ...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
This paper is aimed at the evaluation of the thermal conductivity of ceramic pebble beds which are o...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket ...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
The Helium Cooled Pebble Bed (HCPB) Blanket is one of the reference concepts for the European Breedi...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
Within the framework of the R&D activities promoted by EFDA on the Helium-Cooled Pebble Bed Test Bla...
The thermal stress on breeding blanket structure is one of the main design driver; consequently, an ...
Among the international fusion solid breeder blanket community, there exists steady progress on the ...
Among the international fusion solid breeder blanket community, there exists steady progress on the ...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
In the framework of the European Fusion Technology Programme, Lithium ceramics and Beryllium packed ...
An open issue for fusion power reactor is to design a suitable breeding blanket capable to produce t...
This paper is aimed at the evaluation of the thermal conductivity of ceramic pebble beds which are o...
An open issue for fusion power reactor is the possibility to obtain Tritium in the breeding blanket....