The European contribution to the development of the ITER NB injector

Masiello, A.; Agarici, G.; Bonicelli, T.; Simon, M.; Alonso, Javier; Bigi, M.; Boilson, D.; Chitarin, G.; Day, Christian; Franzen, P.; Hanke, Stefanie; Heinemann, B.; Hemsworth, R.; Luchetta, A.; Marcuzzi, D.; Milnes, J.; Minea, Tiberiu; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Rigato, W.; Sonato, P.; Toigo, V.; Villecroze, F.; Waldon, C.; Zaccaria, P.

doi:10.1016/j.fusengdes.2011.03.035

Cited by 39 publications

(22 citation statements)

References 12 publications

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“…The European ITER domestic agency F4E has defined an R&D roadmap in order to fulfill the development of the ITER HNB facility. 3 A prototype RF source has been developed at the Max-Planck-Institut für Plasmaphysik (IPP) Garching in the past, which has become the ITER reference design in 2007. 4 The negative hydrogen ion source is based on surface production of negative ions on a caesiated grid: hydrogen atoms and positive ions, produced in a low pressure, low temperature hydrogen plasma are converted to negative hydrogen ions on a surface with low work function.…”

Section: Introductionmentioning

confidence: 99%

Extraction of negative charges from an ion source: Transition from an electron repelling to an electron attracting plasma close to the extraction surface

Wimmer

Fantz

NNBI-Team³

2016

Journal of Applied Physics

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Large-scale sources for negative hydrogen ions, capable of delivering an extracted ion current of several ten amperes, are a key component of the neutral beam injection system of the upcoming ITER fusion device. Since the created heat load of the inevitably co-extracted electrons after magnetic separation from the extracted beam limits their tolerable amount, special care must be taken for the reduction of coextracted electrons -in particular in deuterium operation, where the larger amount of co-extracted electrons often limits the source performance. By biasing the plasma grid (PG, first grid of the extraction system) positively with respect to the source body the plasma sheath in front of the PG can be changed from an electron repelling towards an electron attracting sheath. In this way, the flux of charged particles onto the PG can be varied, thus changing the bias current and inverse to it the amount of co-extracted electrons. The PG bias affects also the flux of surface-produced H − towards the plasma volume as well as the plasma symmetry in front of the plasma grid, strongly influenced by an ⃗ E × ⃗ B drift. The influence of varying PG sheath potential profile on the plasma drift, the negative hydrogen ion density and the source performance at the prototype H − source is presented, comparing hydrogen and deuterium operation. The transition in the PG sheath profile takes place in both isotopes, with a minimum of co-extracted electrons formed in case of the electron attracting PG sheath. The co-extracted electron density in deuterium operation is higher than in hydrogen operation, which is accompanied by an increased plasma density in deuterium.

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Section: Introductionmentioning

confidence: 99%

Extraction of negative charges from an ion source: Transition from an electron repelling to an electron attracting plasma close to the extraction surface

Wimmer

Fantz

NNBI-Team³

2016

Journal of Applied Physics

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“…In order to fulfill the ITER requirements, a roadmap towards the ITER source has been defined by the European ITER domestic agency F4E in the past [1]. The RF-driven IPP (Max-Planck-Institut für Plasmaphysik, Garching, Germany) prototype source has become the reference design for the ITER heating neutral beam (HNB) facility in 2007 [2].…”

Section: Introductionmentioning

confidence: 99%

Dependence of the source performance on plasma parameters at the BATMAN test facility

2015

AIP Conference Proceedings

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“…2(k) and 2(l)). The dissociation of the molecules, supported by the dissociation of the 2 H -ions, is the main contributor to the energy gain of the atoms in the discharge volume and, in particular, in the large area chamber. This determines a thermal diffusion flux directed from the large area chamber towards the walls.…”

Section: Fluxes and Discharge Regimementioning

confidence: 99%

“…The on-going work on the design and construction of the ITER Heating Neutral Beam Injector system [1,2] pushes activities on clarifying the bases of the operation of its rf plasma source, started with modeling of the twochamber inductively driven rf sources [3 7] with the design of the BATMAN source [8], in its actual size and as small scale arrangements, and currently tending towards modeling [9 11] of multi-chamber sources as SPIDER [12,13].…”

Section: Introductionmentioning

confidence: 99%