L'objectif de ce travail était d'élaborer un matériau à gradient de propriétés fonctionnelles (MGF) W/Cu afin de remplacer la couche de compliance (Cu-OFHC) dans les composants face au plasma des machines de fusion thermonucléaire de type ITER. La particularité de ce travail étant de réaliser ces matériaux sans dépasser la température de fusion du cuivre dans le but de contrôler la microstructure des matériaux. Le cofrittage est la solution la plus attractive pour les réaliser. La première étape du travail a donc été de diminuer la température de frittage du tungstène afin de réaliser ce cofrittage. La mise en forme d'un MGF continus étant délicat, des calculs thermomécaniques ont été réalisés afin de déterminer le nombre et la composition ...
The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and remov...
An overview of materials foreseen for use or already used in fusion devices is given. The operating ...
As structural materials for future fusion power plants, reduced activation ferritic martensitic stee...
The objective of this study was to develop a Functionally Graded Material (FGM) W / Cu to replace th...
One of the most difficult topics in the design and development of future fusion devices, e.g. ITER (...
One of the most difficult topics in the design and development of future fusion devices, e.g. ITER (...
Plasma facing components in fusion devices have to withstand extreme thermal loads. To fulfil the de...
This work aims to process W-Cu FGM for fusion material applications, in particular plasma facing com...
Functionally graded materials (FGMs) have the potential to reduce high stress concentrations near ma...
28th Symposium on Fusion Technology (SOFT), San Sebastian, SPAIN, SEP 29-OCT 03, 2014International a...
The thermal stress between W plasma-facing material (PFM) and Cu heat sink in fusion reactors can be...
The ITER tokamak, the experimental fusion reactor designed to be the first to produce net energy, ha...
A substantial contribution of the stresses that arise inside the Plasma-Facing Components (PFCs) whe...
La technologie de plasma inductif est proposée pour la fabrication des dépôts de tungstène et de mol...
For a future commercial fusion reactor the First Wall of the breeding blanket will require a joint b...
The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and remov...
An overview of materials foreseen for use or already used in fusion devices is given. The operating ...
As structural materials for future fusion power plants, reduced activation ferritic martensitic stee...
The objective of this study was to develop a Functionally Graded Material (FGM) W / Cu to replace th...
One of the most difficult topics in the design and development of future fusion devices, e.g. ITER (...
One of the most difficult topics in the design and development of future fusion devices, e.g. ITER (...
Plasma facing components in fusion devices have to withstand extreme thermal loads. To fulfil the de...
This work aims to process W-Cu FGM for fusion material applications, in particular plasma facing com...
Functionally graded materials (FGMs) have the potential to reduce high stress concentrations near ma...
28th Symposium on Fusion Technology (SOFT), San Sebastian, SPAIN, SEP 29-OCT 03, 2014International a...
The thermal stress between W plasma-facing material (PFM) and Cu heat sink in fusion reactors can be...
The ITER tokamak, the experimental fusion reactor designed to be the first to produce net energy, ha...
A substantial contribution of the stresses that arise inside the Plasma-Facing Components (PFCs) whe...
La technologie de plasma inductif est proposée pour la fabrication des dépôts de tungstène et de mol...
For a future commercial fusion reactor the First Wall of the breeding blanket will require a joint b...
The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and remov...
An overview of materials foreseen for use or already used in fusion devices is given. The operating ...
As structural materials for future fusion power plants, reduced activation ferritic martensitic stee...