The main purpose of the Divertor Tokamak Test facility (DTT) is to study alternative solutions to mitigate the issue of the power exhaust, under integrated physics and technical conditions relevant for ITER and DEMO. One of the most complex and innovative subsystems of the entire project is certainly the negative-ion-based Neutral Beam Injector (NBI), meant to couple to the plasma deuterium neutrals (D0) with an energy of 510 keV and an injected power of 10 MW. This contribution describes the conceptual design of the beamline for the DTT NBI system, with a particular focus on the new technical solutions adopted to fulfill the requirements and maximize the performances. The DTT NBI is required to operate with high efficiency in several operating scenarios, i.e. in a large range of beam energies, between 10% and 100% of the nominal value (510 keV). To reach this challenging goal, an innovative accelerator design, featuring sphereshaped grids and hyperlens grids, has been developed. The implementation of this design concept of the accelerator has recently become possible thanks to recent improvements of the additive manufacturing technology. A second relevant innovation of the DTT NBI compared to the existing devices regards the vacuum pumping system, which will be based on Non-Evaporable Getter (NEG) pumps. This will represent the first application of the NEG technology to an NBI for the heating and current drive system of a fusion experiment, with a possible simplification of the overall construction compared to typical solutions with cryogenic pumps. A third important innovation is the possible usage, currently under consideration, of the Modular Multilevel Converters for the high voltage power supply. A detailed quantitative analysis of the main design choices will be provided, together with the lines of the project future developments.
Innovative concepts in the DTT Neutral Beam Injector
Agostinetti P.
Related products
-
21st joint workshop on electron cyclotron emission (ECE) and electron cyclotron resonance heating (ECRH), , Saint-Paul-lez-Durance, France , 20-24 June 2022 Year: 2022
Development of ECRH-based methods for assisted discharge recovery: experiment and simulation
Ricci D.; Stober J.; Dux R.; Figini L.; Wauters T.; Lerche E.; Granucci G.; the ASDEX Upgrade Team
-
Workshop on Electric Fields, Turbulence and Self-Organization Magentized Plasmas (EFTSOMP 2019), , Padova, Italy , 15-16 July 2019 Year: 2019
Study of the role of divertor neutrals and SOL turbulence in the density shoulder formation and evolution in ASDEX Upgrade
Agostini M.; Vianello N.; Carraro L.; Carralero D.; Cavedon M.; Dux R.; Lunt T.; Naulin V.; Spolaore M.; Wolfrum E.; ASDEX Upgrade Team; EUROfusion MST1 Team
-
Technical Meeting on Synergies in Technology Development between Nuclear Fission and Fusion for Energy Production, , Vienna and online , 6-10 June 2022 Year: 2022
PILOT HYBRID EXPERIMENT WITH REVERSED FIELD PINCH AS NEUTRON SOURCE AND DOUBLE FISSION TEST BEDS: AN INNOVATIVE STAGE APPROACH TOWARDS A FULL POWER FUSION-FISSION HYBRID REACTOR
Piovan R.; Agostinetti P.; Bustreo C.; Cavazzana R.; Cemmi A.; Ciotti M.; Cherubini N.; Escande D.E.; Gaio E.; Lomonaco G.; Lunardon F.; Maistrello A.; Marrelli L.; Murgo S.; Orsitto F.P.; Osipenko M.; Panza F.; Pompeo N.; Puiatti M.E.; Ricco G.; Ripani M.; Valisa M.; Zollino G.; Zuin M.
-
48th EPS Conference on Plasma Physics, , Online, Amsterdam timezone , 27 June - 1 July 2022 Year: 2022
Predict-first scenario modelling in support of the design of the Divertor Tokamak Test facility
Casiraghi I.; Mantica P.; Ambrosino R.; Aucone L.; Auriemma F.; Baiocchi B.; Balbinot L.; Barberis T.; Bonanomi N.; Castaldo A.; Citrin J.; Frassinetti L.; Innocente P.; Koechl F.; Mariani A.; Nowak S.; Agostinetti P.; Ceccuzzi S.; Figini L.; Granucci G.; Valisa M.
English
Italiano