On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

Toigo, V.; Marcuzzi, D.; Serianni, G.; Boldrin, M.; Chitarin, G.; Bello, S. Dal; Grando, L.; Luchetta, A.; Pasqualotto, R.; Zaccaria, P.; Zanotto, L.; Agnello, R.; Agostinetti, P.; Agostini, M.; Antoni, V.; Aprile, D.; Barbisan, M.; Battistella, M.; Berton, G.; Bigi, M.; Brombin, M.; Candeloro, V.; Canton, A.; Casagrande, Riccardo; Cavallini, C.; Cavazzana, R.; Cordaro, Luigi; Cruz, N.; Palma, M. Dalla; Dan, M.; Lorenzi, A. De; Delogu, R.; Muri, M. De; Denizeau, S.; Fadone, M.; Fellin, F.; Ferro, A.; Gaio, E.; Gasparini, F.; Gasparrini, Claudia; Gnesotto, F.; Jain, Palak; Krastev, P. I.; López‐Bruna, D.; Lorenzini, R.; Maistrello, A.; Manduchi, G.; Manfrin, S.; Marconato, N.; Martines, E.; Martini, Geórgia Ribeiro; Martini, S.; Milazzo, Ruggero; Patton, T.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Poggi, C.; Pomaro, N.; Duteil, Basile Pouradier; Recchia, M.; Garola, Andrea Rigoni; Rizzolo, A.; Sartori, E.; Shepherd, A.; Siragusa, M.; Sonato, P.; Sottocornola, Alessandro; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Terranova, D.; Tinti, P.; Tomsic, P.; Trevisan, L.; Ugoletti, M.; Valente, M.; Vignando, M.; Zagórski, R.; Zamengo, A.; Zaniol, B.; Zaupa, M.; Zuin, M.; Cavenago, M.; Boilson, D.; Rotti, C.; Veltri, P.; Decamps, Hans; Dremel, M.; Graceffa, J.; Geli, F.; Urbani, M.; Zacks, J.; Bonicelli, T.; Paolucci, Francesco; Garbuglia, A.; Agarici, G.; Gomez, G.; Gutiérrez, Daniel; Kouzmenko, G.; Labate, C.; Masiello, A.; Mico, G.; Moreno, J.F.; Pilard, V.; Rousseau, Anthony; Simon, M.; Kashiwagi, M.; Tobari, H.; Watanabe, K.; Maejima, Tetsuya; Kojima, Akira; Oshita, E.; Yamashita, Yasuo; Konno, Shota; Singh, Manoj; Chakraborty, Arun; Patel, Hitesh; Singh, Narinder; Fantz, U.; Bonomo, F.; Cristofaro, S.; Heinemann, B.; Kraus, Werner; Wimmer, Christian; Wünderlich, D.; Fubiani, G.; Tsumori, K.; Croci, G.; Gorini, G.; McCormack, O.; Muraro, A.; Rebaı̈, M.; Tardocchi, M.; Giacomelli, L.; Rigamonti, D.; Taccogna, F.; Bruno, D.; Rutigliano, M.; D’Arienzo, Marco; Tonti, Andrea; Panin, F.

doi:10.1016/j.fusengdes.2021.112622

Cited by 48 publications

(25 citation statements)

References 40 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The full-size source will be commissioned and operated at the European Neutral Beam Test Facility (NBTF) in Padua, Italy [11]. The NBTF hosts a test facility for the ITER NBI ion source (Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma, SPIDER), which went into operation in 2018 [12,13]. The second test facility that represents the full prototype beamline of the HNB of ITER (Megavolt ITER Injector and Concept Advancement, MITICA) is currently planned to go into full operation in 2024 [14].…”

Section: Introductionmentioning

confidence: 99%

Negative Hydrogen Ion Sources for Fusion: From Plasma Generation to Beam Properties

et al. 2021

Self Cite

View full text Add to dashboard Cite

The neutral beam injection systems for the international fusion experiment ITER used for heating, current drive, and diagnostic purposes are based on RF-driven negative hydrogen ion sources with a source area of roughly 0.9 m × 1.9 m. The sources operate at 0.3 Pa in hydrogen and in deuterium using a total available RF generator power of 800 kW per source at a frequency of 1 MHz. In order to fulfill the challenging requirements for ITER and beyond (like a DEMOnstration power plant, DEMO), worldwide developments are underway addressing the topics of plasma generation, ion extraction together with the issue of reducing and stabilizing the co-extracted electron current, and the beam properties. At the example of the activities at the ITER prototype source and the size scaling experiment ELISE, the present status and its challenges are summarized. The RF power transfer efficiency of these sources is only about 65% in maximum, giving significant room for improvements to relax the demands on the RF generator and ensure reliable operation. The plasma uniformity in front of the large extraction system is the result of plasma drifts. They have a huge impact on the nonuniformity of the co-extracted electrons and influence the ions and thus the beam properties as well. Understanding the optics of such large beams composed of hundreds of beamlets is a crucial task and is under continuous improvement. The main challenge, however, is still the fulfillment of the ITER requirements for deuterium, in particular, for long pulses. The management of caesium, which is evaporated into the source to generate sufficient negative ions by the surface conversion process, is one of the keys for stable and reliable operation.

show abstract

Section: Introductionmentioning

confidence: 99%

Negative Hydrogen Ion Sources for Fusion: From Plasma Generation to Beam Properties

et al. 2021

Self Cite

View full text Add to dashboard Cite

show abstract

“…The inductively coupled plasma (ICP) sources are used in RF ion sources for fusion and accelerator application [1,2]. A sketch of a cylindrical ICP source is shown in figure 1.…”

Section: Introductionmentioning

confidence: 99%

“…The Faraday shield (FS), a thin-wall metal structure with slits, is placed between the coil and the plasma to reduce capacitive coupling [3]. Besides, in high-power RF ion sources, FS is placed in contact with the plasma to protect the dielectric tube from erosion [1]. The RF power from the coil is coupled to the plasma through the slits of FS, which makes FS an important component of ICP sources.…”

Section: Introductionmentioning

confidence: 99%

“…The RF power from the coil is coupled to the plasma through the slits of FS, which makes FS an important component of ICP sources. There are some 2D electromagnetic models to obtain the field inside ICP sources with FS: semianalytical one with FS and without plasma [4], numerical ones with FS and plasma approximated as a good conductor [1], and analytical one with infinitely thin FS and without plasma [5]. Based on the models with either plasma [3] or finitely thin FS [4], a 2D semi-analytical model considering both FS and plasma is proposed in this contribution.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

A 2D semi-analytical electromagnetic model for cylindrical ICP sources with Faraday shield

Yang

Zhou

et al. 2022

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

Faraday shield(FS) is a metallic shield with slits through which electromagnetic energy is coupled into cylindrical ICP sources. Thus, the effect of FS on the RF field and power coupling is important. A 2D semi-analytical electromagnetic model considering both FS and plasma is proposed. The results compared to a 2D numerical model shows that the semi-analytical model is available in electromagnetic field calculations. It is found that both FS and plasma have no influence on the magnetic field outside them. FS strengthens the electric field around the slits and weakens the electric field around the middle of the stripes, and this effect is due to the gradient field generated by the electric charge accumulated on the FS surfaces. From the point of view of the pure 2D electromagnetic field, FS affects the electric field distribution in a small region, and it seems to not affect the total power coupling into plasma.

show abstract

“…SPIDER (Source for the Production of Ions of Deuterium Extracted from Radiofrequency plasma) is the full-scale prototype of the ITER NBI (Neutral Beam Injector) ion source [1][2][3]. In SPIDER beam source, RF inductively coupled plasma drivers are used to produce hydrogen or deuterium plasma, from which negative ions are electrostatically accelerated by means of a series of grids.…”

Section: Introductionmentioning

confidence: 99%

Study of RF Stray Currents in ITER Neutral Beam Test Facilities

et al. 2021

View full text Add to dashboard Cite

The operation of SPIDER (Source for the Production of Ions of Deuterium Extracted from Radio-frequency plasma), full-scale prototype of ITER NBI (Neutral Beam Injector) radio-frequency ion source, pointed out deleterious effects caused by stray Radio-Frequency (RF) currents flowing in the electrical equipment not included in the RF power system. MITICA (Megavolt ITER Injector and Concept Advancement), the full-scale prototype of ITER NBI, is characterized by a similar design in terms of layout of the power supplies and connections to the beam source; thus, it is expected to be subject to the RF stray currents problem. SPIDER RF system is composed of four RF generators, four coaxial lines and four RF loads. Each RF generator is rated for operation at 200 kW in the frequency range 0.9 ÷ 1.1 MHz. The power is delivered to the four loads via as many RF coaxial lines, housed inside a multiconductor transmission line. Each load consists of a capacitive matching network and two plasma drivers in series. Due to the presence of stray connections at the generator and beam-source side (e.g., parasitic capacitances), unwanted RF currents can flow through alternative paths and negatively affect the components not intended for transmission of RF power, the output stages of power supplies and several diagnostics installed in the High-Voltage Deck (HVD) and at the beam source. This paper presents the development of a circuital model used to estimate the RF stray currents in SPIDER electrical system; the understanding of this phenomenon and the development of a model with predictive capabilities is fundamental for the assessment of the performance of both SPIDER and MITICA and, in general, of alternative RF system layouts with respect to the stray currents issue.

show abstract

On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

Cited by 48 publications

References 40 publications

Negative Hydrogen Ion Sources for Fusion: From Plasma Generation to Beam Properties

Negative Hydrogen Ion Sources for Fusion: From Plasma Generation to Beam Properties

A 2D semi-analytical electromagnetic model for cylindrical ICP sources with Faraday shield

Study of RF Stray Currents in ITER Neutral Beam Test Facilities

Contact Info

Product

Resources

About