First experiments with the negative ion source NIO1

Cavenago, M.; Serianni, G.; Muri, M. De; Agostinetti, P.; Antoni, V.; Baltador, C.; Barbisan, M.; Baseggio, L.; Bigi, M.; Cervaro, V.; Agostini, F. Degli; Fagotti, E.; Kulevoy, T. V.; Ippolito, N.; Laterza, B.; Minarello, A.; Maniero, M.; Pasqualotto, R.; Petrenko, S. V.; Poggi, M.; Ravarotto, D.; Recchia, M.; Sartori, E.; Sattin, M.; Sonato, P.; Taccogna, F.; Variale, V.; Veltri, P.; Zaniol, B.; Zanotto, L.; Zucchetti, S.

doi:10.1063/1.4932616

Cited by 31 publications

(14 citation statements)

References 14 publications

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“…Other diagnostics that are required at the beginning of SPIDER operation (thermocouples, emission and laser spectroscopy, electrostatic probes, visible and infrared (IR) imaging) are almost ready including vacuum windows and the integration with the data acquisition system, while other ones still need R&D to be completed [28]. Prototypes, like tomography cameras, and full setups from sensor to acquisition system, basic analysis and visualization software codes, like those for thermocouples and IR cameras, are being tested at the NIO1 RF source test facility in operation at Consorzio RFX in Padova [29].…”

Section: Spider Calorimeters and Diagnosticsmentioning

confidence: 99%

“…The combined use of these codes was systematically benchmarked against the experimental results obtained in the test facilities of the collaborating laboratories of QST (formerly JAEA), Naka (Japan) [108][109][110], IPP, Garching (Germany) [111], NIFS, Gifu (Japan) [112,113] and NIO1 [114,115], which is a flexible and modular beam source dedicated to providing a model for the larger sources and a versatile test bench for numerical models and innovative techniques operating in the CNR research area, where PRIMA is also located.…”

Section: Numerical Toolsmentioning

confidence: 99%

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The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors

Toigo¹,

Piovan²,

Bello³

et al. 2017

New J. Phys.

157

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The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on ITER Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of the ITER heating neutral beam injector, and SPIDER, the full-size radio frequency negative-ions source. The NBTF realization and the exploitation of SPIDER and MITICA have been recognized as necessary to make the future operation of the ITER heating neutral beam injectors efficient and reliable, fundamental to the achievement of thermonuclear-relevant plasma parameters in ITER. This paper reports on design and R&D carried out to construct PRIMA, SPIDER and MITICA, and highlights the huge progress made in just a few years, from the signature of the agreement for the NBTF realization in 2011, up to now-when the buildings and relevant infrastructures have been completed, SPIDER is entering the integrated commissioning phase and the procurements of several MITICA components are at a well advanced stage.

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Section: Spider Calorimeters and Diagnosticsmentioning

confidence: 99%

Section: Numerical Toolsmentioning

confidence: 99%

The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors

Toigo¹,

Piovan²,

Bello³

et al. 2017

New J. Phys.

157

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“…The test of such a system in the small negative ion beam system NIO1 the topic of this paper, which describes the feasibility study for a beam driven plasma neutralizer test in a small ion source such as NIO1 [16,17]. Due to its versatility NIO ion source is considered for testing other advanced concept for NBIs [18].…”

Section: Neutralization Efficiency and Beam-driven Plasma Neutralizersmentioning

confidence: 99%

Preliminary studies for a beam-generated plasma neutralizer test in NIO1

Sartori

Veltri

Balbinot

et al. 2017

AIP Conference Proceedings

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“…The resulting negative ion beam at 1 MeV, after passing through a gas cell neutraliser and an electrostatic residual ion dump (RID), should produce a ∼17 MW neutral beam focused onto a target calorimeter for a duration up to 3600 s.Source for production of ions of deuterium extracted from RF plasma (SPIDER) [5] is a full-size test-bed of the ion source and extractor for the ITER heating NBI and it will operate at an acceleration voltage of 100 kV at the same current and pulse duration. A CAD view of SPIDER is shown in figure 3.In the vicinity of PRIMA, a small and versatile negative ion source, dubbed negative ion optimisation (NIO1) [6], is under operation with the aim of producing a 130 mA negative hydrogen current, divided into 3×3 apertures and accelerated to 60 kV; unlike SPIDER and MITICA, NIO1 is operated continuously [7].…”

mentioning

confidence: 99%

Neutralisation and transport of negative ion beams: physics and diagnostics

Serianni¹,

Agostinetti²,

Agostini³

et al. 2017

New J. Phys.

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Neutral beam injection is one of the most important methods of plasma heating in thermonuclear fusion experiments, allowing the attainment of fusion conditions as well as driving the plasma current. Neutral beams are generally produced by electrostatically accelerating ions, which are neutralised before injection into the magnetised plasma. At the particle energy required for the most advanced thermonuclear devices and particularly for ITER, neutralisation of positive ions is very inefficient so that negative ions are used. The present paper is devoted to the description of the phenomena occurring when a high-power multi-ampere negative ion beam travels from the beam source towards the plasma. Simulation of the trajectory of the beam and of its features requires various numerical codes, which must take into account all relevant phenomena. The leitmotiv is represented by the interaction of the beam with the background gas. The main outcome is the partial neutralisation of the beam particles, but ionisation of the background gas also occurs, with several physical and technological consequences. Diagnostic methods capable of investigating the beam properties and of assessing the relevance of the various phenomena will be discussed. Examples will be given regarding the measurements collected in the small flexible NIO1 source and regarding the expected results of the prototype of the neutral beam injectors for ITER. The tight connection between measurements and simulations in view of the operation of the beam is highlighted. operating in the existing tokamaks. Consequently, PRIMA, the ITER Neutral Beam Test Facility [2], was set up to constitute a test-bed, where the solutions to all the issues related to the achievement of full performances in the heating NBI system for ITER are going to be addressed and optimised, particularly regarding critical aspects like density and uniformity of the extracted negative ion current, high voltage holding and heat loads on the components [3]. Megavolt ITER Injector Concept Advancement (MITICA) is the full-scale prototype of the ITER NBIs [4]; it includes an RF-driven plasma source for the production of negative ions and should operate at a pressure as low as 0.3 Pa in hydrogen or deuterium gasses. The negative ions are produced on the surface of the grid (Plasma Grid, PG) that closes the plasma region; their production is enhanced thanks to a thin caesium layer continuously deposited over the PG by evaporation. Negative ions are extracted through the 1280 apertures in the PG by application of a suitable positive voltage to the extraction grid (EG), located just downstream of the PG. The RF plasma source operates at an applied electric potential of about −1 MV. Five additional acceleration grids (AG1, AG2, AG3, AG4, GG), at intermediate electric potential increasing by 200 kV steps, are located downstream with respect to the EG, thus constituting a 5-stage electrostatic accelerator. The resulting negative ion beam at 1 MeV, after passing through a gas cell neutraliser and an electro...

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First experiments with the negative ion source NIO1

Cited by 31 publications

References 14 publications

The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors

The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors

Preliminary studies for a beam-generated plasma neutralizer test in NIO1

Neutralisation and transport of negative ion beams: physics and diagnostics

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