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Progress in the ITER neutral beam test facility

Toigo, V.; Dal Bello, S.; Bigi, M.; Boldrin, M.; Chitarin, G.; Grando, L.; Luchetta, A.; Marcuzzi, D.; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Zaccaria, P.; Zanotto, L.; Agostinetti, P.; Agostini, M.; Antoni, V; Aprile, D.; Barbisan, M.; Battistella, M.; Brombin, M.; Cavazzana, R.; Dalla Palma, M.; Dan, M.; Denizeau, S.; De Lorenzi, A.; Delogu, R.; De Muri, M.; Fadone, M.; Fellin, F.; Ferro, A.; Fiorentin, A.; Gaio, E.; Gambetta, G.; Gasparini, F.; Gnesotto, F.; Jain, P.; Maistrello, A.; Manduchi, G.; Manfrin, S.; Marchiori, G.; Marconato, N.; Moresco, M.; Ocello, E.; Patton, T.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Piovan, R.; Poggi, C.; Recchia, M.; Rizzolo, A.; Rostagni, G.; Sartori, E.; Siragusa, M.; Sonato, P.; Sottocornola, A.; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Tinti, P.; Ugoletti, M.; Valente, M.; Zamengo, A.; Zaniol, B.; Zaupa, M.; Boilson, D.; Rotti, C.; Veltri, P.; Chareyre, J.; Decamps, H.; Dremel, M.; Graceffa, J.; Geli, F.; Schunke, B.; Svensson, L.; Urbani, M.; Bonicelli, T.; Agarici, G.; Garbuglia, A.; Masiello, A.; Paolucci, F.; Simon, M.; Badly-Maitre, L.; Bragulat, E.; Gomez, G.; Gutierrez, D.; Labate, C.; Mico, G.; Moreno, J. F.; Pilard, V; Kouzmenko, G.; Rousseau, A.; Kashiwagi, M.; Tobari, H.; Watanabe, K.; Maejima, T.; Kojima, A.; Umeda, N.; Sasaki, S.; Chakraborty, A.; Baruah, U.; Patel, H.; Singh, N. P.; Patel, A.; Dhola, H.; Raval, B.; Gupta, V; Fantz, U.; Heinemann, B.; Kraus, W.; Cavenago, M.; Hanke, S.; Ochoa, S.; Blatchford, P.; Chuilon, B.; Xue, Y.; Croct, G.; Gorini, G.; Muraro, A.; Rebai, M.; Tardocchi, M.; D’Arienzo, M.; Sandri, S.; Tonti, A.; Panin, F.

Heating neutral beam (HNB) injectors, necessary to achieve burning conditions and to control plasma instabilities in ITER, are characterized by such demanding parameters that a neutral beam test facility (NBTF) dedicated to their development and optimization is being realized in Padua (Italy) with direct contributions from the Italian government (through Consorzio RFX as the host entity) and the ITER international organization (with kind contributions from the ITER domestic agencies of Europe, Japan and India) and technical and scientific support from various European laboratories and universities. The NBTF hosts two experiments: SPIDER, devoted to ion source optimization for the required source performance, and MITICA, the full-size prototype of the ITER HNB, with an ion source identical to SPIDER. This paper gives an overview of the progress towards NBTF realization, with particular emphasis on issues discovered during this phase of activity and on solutions adopted to minimize the impact on the schedule and maintain the goals of the facilities. The realization of MITICA is well advanced; operation is expected to start in 2023 due to the long procurement time of the in-vessel mechanical components. The beam source power supplies, operating at 1 MV, are in an advanced phase of realization; all high-voltage components have been installed and the complex insulation test phase began in 2018. At the same time, construction and installation of SPIDER plant systems was successfully completed with their integration into the facility. The mechanical components of the SPIDER ion source were installed inside the vessel and connected to the plants. Integrated commissioning with the control, protection and safety systems ended positively and the first experimental phase has begun. The first results of the SPIDER experiment, with data from operational diagnostics, and the plans for the 1 MV insulation tests on the MITICA high-voltage components are presented.

ID 404929
DOI 10.1088/1741-4326/ab2271
PRODUCT TYPE Journal Article
LAST UPDATE 2023-06-30T13:15:32Z
TITLE Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium