In the full-tungsten divertor qualification program at ITER Organization, macro-cracks, so called self-castellation were found in a fraction of tungsten monoblocks during cyclic high heat flux loading at 20MW/m2. The number of monoblocks with macro-cracks varied with the tungsten products used as armour material. In order to understand correlation between the macro-crack appearance and W properties, an activity to characterize W monoblock materials was launched at the IO. The outcome highlighted that the higher the recrystallization resistance, the lower the number of cracks detected during high heat flux tests. Thermo-mechanical finite element modelling demonstrated that the maximum surface temperature ranges from 1800 °C to 2200 °C and in...
The lifetime of the divertor in tokamak nuclear fusion reactors is uncertain, due to the severe heat...
The recrystallization assisted microstructural changes during cyclic heat exposure are surmised detr...
It is highly desirable to understand the long term evolution of the divertor material under the extr...
In the full-tungsten divertor qualification program at ITER Organization, macro-cracks, so called se...
AbstractSince the ITER divertor design includes tungsten monoblocks in the vertical target where hea...
The lifetime of tungsten (W) monoblocks under fusion conditions is ambivalent. In this work, the mic...
Extending the lifetime of tungsten based plasma facing components for future fusion reactors remains...
In order to evaluate the option to start the ITER operation with a full tungsten (W) divertor, high ...
Crack formation in an ITER-reference tungsten grade was examined under single thermal shock loading....
In nuclear fusion devices the surfaces directly facing the plasma are irradiated with high energy fl...
In preparation of the production of the actively cooled tungsten targets for the lower divertor of W...
In the context of using a full-tungsten (W) divertor for ITER, thermal shock resistance has become e...
The influence of recrystallization on thermal shock resistance has been identified as an issue that ...
Plasma facing components inside future nuclear fusion reactors are subjected to a high heat load and...
The lifetime of the divertor in tokamak nuclear fusion reactors is uncertain, due to the severe heat...
The recrystallization assisted microstructural changes during cyclic heat exposure are surmised detr...
It is highly desirable to understand the long term evolution of the divertor material under the extr...
In the full-tungsten divertor qualification program at ITER Organization, macro-cracks, so called se...
AbstractSince the ITER divertor design includes tungsten monoblocks in the vertical target where hea...
The lifetime of tungsten (W) monoblocks under fusion conditions is ambivalent. In this work, the mic...
Extending the lifetime of tungsten based plasma facing components for future fusion reactors remains...
In order to evaluate the option to start the ITER operation with a full tungsten (W) divertor, high ...
Crack formation in an ITER-reference tungsten grade was examined under single thermal shock loading....
In nuclear fusion devices the surfaces directly facing the plasma are irradiated with high energy fl...
In preparation of the production of the actively cooled tungsten targets for the lower divertor of W...
In the context of using a full-tungsten (W) divertor for ITER, thermal shock resistance has become e...
The influence of recrystallization on thermal shock resistance has been identified as an issue that ...
Plasma facing components inside future nuclear fusion reactors are subjected to a high heat load and...
The lifetime of the divertor in tokamak nuclear fusion reactors is uncertain, due to the severe heat...
The recrystallization assisted microstructural changes during cyclic heat exposure are surmised detr...
It is highly desirable to understand the long term evolution of the divertor material under the extr...