R. De Luca

Status of design and manufacturing qualification activities of the first wall of the Divertor Tokamak test facility

M. Furno Palumbo, S. Roccella, G. De Sano, R. De Luca et autres

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Investigation of laser powder bed fusion for the application of additive manufacturing in the First Wall of the DTT facility

G. De Sano, M. Furno Palumbo, R. De Luca, G. Dose et autres

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Thermo-structural assessment of the limiter inboard first wall design of the Divertor Tokamak Test facility

R. De Luca, Maurizio Furno Palumbo, P. Frosi, G. De Sano et autres

The Divertor Tokamak Test facility (DTT) aims at investigating integrated power exhaust solutions that can be relevant for DEMO and future power plants. Such an ambitious goal imposes several constraints on the engineering design of the actively cooled plasma-facing components (PFCs) of …

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Feasibility study of the DEMO divertor target baffles

F. Crescenzi, M. Cerocchi, R. De Luca, F. Giorgetti et autres

The divertor is one of the key components of a Tokamak fusion machine since it must be capable to exhaust both particles and power. Since the CAD model has been released the DEMO Outboard Vertical Target baffles (OVT) represent one of the …

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Diffusion bonding between tungsten base tiles and copper for fusion applications

F. Giorgetti, Pierdomenico Lorusso, M. Cerocchi, Francesco Crea et autres

In the R&D of plasma facing components fabrication, it is required to develop joining technologies between dissimilar materials resistant to strong thermal gradients. When, as in the divertor or in a few positions of the First Wall, the thermal loads exceed 1 …

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Fabrication of DEMO divertor target mock-up by HRP technology with tungsten fiber reinforced tungsten as armour material

Francesco Crea, E. Cacciotti, R. De Luca, Pierdomenico Lorusso et autres

The current consolidated process for the fabrication of a target divertor for ITER foresees armour material monoblocks with Oxygen Free Electronic Grade copper (OFE-Cu, Cu) interlayer joined to CuCrZr ITER Grade (CuCrZr-IG) cooling pipes by diffusion bonding . ENEA's Special Technologies Laboratory …

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Non-destructive ultrasonic inspections of small-scale mock-ups provided with advanced tungsten armours for DEMO divertor target

R. De Luca, E. Cacciotti, M. Cerocchi, Francesco Crea et autres

Within the framework of the EUROfusion Consortium, the Characterization of armour, heat sinks materials and joints sub-project of the Work Package Material (WP-MAT) has been dedicated to the development of different tungsten (W) monoblock mock-ups equipped with advanced materials for divertor target …

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Development of tungsten fiber-reinforced copper composite pipes for EU-DEMO Divertor target

Pierdomenico Lorusso, S. Roccella, E. Cacciotti, M. Cerocchi et autres

Within the roadmap of the EU-DEMO reactor design pursued by the EUROfusion Programme, R&D activities are promoted for the technological development of Plasma Facing Components. A dedicated task aims at consolidating and verifying the current target concepts envisioned for DEMO Divertor, derived …

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Fabrication of DEMO divertor target mock-up by HRP technology with tungsten fiber reinforced tungsten as armour material

Francesco Crea, E. Cacciotti, R. De Luca, Pierdomenico Lorusso et autres

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Divertor Tokamak Test facility project: status of design and implementation

F. Romanelli, Domenico Abate, E. Acampora, D. Agguiaro et autres

Abstract An overview is presented of the progress since 2021 in the construction and scientific programme preparation of the Divertor Tokamak Test (DTT) facility. Licensing for building construction has been granted at the end of 2021. Licensing for Cat. A radiologic source …

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Armor Thickness Assessment for the Divertor Tokamak Test Facility (DTT) Divertor Targets

S. Roccella, F. Giorgetti, R. De Luca, G. De Sano et autres

The Divertor Tokamak Test (DTT) facility is a fusion device under construction in Italy. The mission of DTT is to test alternative divertor concepts under integrated physics and technological conditions that can reliably be extrapolated to DEMO. Due to the plasma core …

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Qualification Activities for the DTT Divertor

F. Giorgetti, S. Roccella, Francesco Crea, G. Dose et autres

The divertor tokamak test (DTT) facility is currently in the design stage and in the initial phase of construction at the research center ENEA Frascati. The DTT facility aims at searching integrated solutions for the power exhaust issue maintaining plasma performances compatible …

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