DTT-Divertor Tokamak Test facility: A testbed for DEMO
R Ambrosino - Fusion Engineering and Design, 2021 - Elsevier
The effective treatment of the heat and power exhaust is a critical issue in the road map to
the realization of the fusion energy. In order to provide possible, reliable, well assessed and …
the realization of the fusion energy. In order to provide possible, reliable, well assessed and …
[HTML][HTML] Additive manufacturing for thermal management applications: from experimental results to numerical modeling
G Favero, M Bonesso, P Rebesan, R Dima… - International Journal of …, 2021 - Elsevier
Abstract Recently, Additive Manufacturing (AM) of metal components has opened new
frontiers in heat transfer applications, going beyond the capabilities of conventional …
frontiers in heat transfer applications, going beyond the capabilities of conventional …
[HTML][HTML] Conceptual design of the DTT ECRH quasi-optical transmission line
Abstract The Divertor Tokamak Test (DTT) facility is being realised in Frascati, Italy for the
study of the power exhaust issues in view of DEMO tokamak. A multi-MW Electron Cyclotron …
study of the power exhaust issues in view of DEMO tokamak. A multi-MW Electron Cyclotron …
[HTML][HTML] Re-design of EU DEMO with a low aspect ratio
The design point that had been chosen for EU DEMO in 2016 is reviewed here and a
modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was …
modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was …
Validation of IMEP on Alcator C-Mod and JET-ILW ELMy H-mode plasmas
T Luda, C Angioni, MG Dunne, E Fable… - Plasma Physics and …, 2023 - iopscience.iop.org
The recently developed integrated model based on engineering parameters (IMEP)(Luda et
al 2020 Nucl. Fusion 61 126048; Luda et al 2021 Nucl. Fusion 60 036023), so far validated …
al 2020 Nucl. Fusion 61 126048; Luda et al 2021 Nucl. Fusion 60 036023), so far validated …
Plasma scenarios for the DTT tokamak with optimized poloidal field coil current waveforms
In the field of nuclear fusion, the power exhaust problem is still an open issue and
represents one of the biggest problems for the realization of a commercial fusion power …
represents one of the biggest problems for the realization of a commercial fusion power …
Systems engineering approach for the iterative concept design and virtual simulation of the DTT hyper redundant manipulator
S Buonocore, G Di Gironimo, M Favaretto… - Fusion Engineering and …, 2023 - Elsevier
This paper proposes a System Engineering-based iterative design approach for the DTT
HyRMan, an hyper redundant manipulator conceived to perform Remote Maintenance (RM) …
HyRMan, an hyper redundant manipulator conceived to perform Remote Maintenance (RM) …
The DTT proposal. A tokamak facility to address exhaust challenges for DEMO: Introduction and executive summary
R Albanese, A Pizzuto, WPDTT2 Team - Fusion Engineering and Design, 2017 - Elsevier
As indicated in the European Fusion Roadmap, the main objective of the Divertor Tokamak
Test facility (DTT) is to explore alternative power exhaust solutions for DEMO so as to …
Test facility (DTT) is to explore alternative power exhaust solutions for DEMO so as to …
SOLPS-ITER modeling of ASDEX Upgrade L-mode detachment states
SOLPS-ITER is used to model ASDEX Upgrade L-mode detachment states including the
onset of detachment, the fluctuating detachment, and the complete detachment states …
onset of detachment, the fluctuating detachment, and the complete detachment states …
Collisionless losses of fast ions in the divertor tokamak test due to toroidal field ripple
G Spizzo, M Gobbin, P Agostinetti, R Albanese… - Nuclear …, 2021 - iopscience.iop.org
In this paper we analyze fast ion motion in the divertor tokamak test (DTT) device (Albanese
et al 2017 Nucl. Fusion 57 016010). It is planned that DTT will be heated through a mix of 45 …
et al 2017 Nucl. Fusion 57 016010). It is planned that DTT will be heated through a mix of 45 …