The achievement of burning plasma in ITER will require at least 33 MW of additional heating transferred to the plasma core by means of two 16.5 MW - 1 MeV injectors (N-NBI - Negative ion based - Neutral Beam Injector) of H or D atoms, with an extracted negative ion current of 40 A (i.e. 40 MW of extracted beam). A third Injector is foreseen as a future upgrade, to increase the power delivery to the ITER plasma up to 50 MW The N-NBI record so far obtained belongs to the Injector of JT60-U, in which have been extracted 17.4 A of negative current, accelerated up to 0.41 MeV. It is evident that the performances required for the ITER N-NBI exceed by far the present capability: for this reason, the Neutral Beam Test Facility - NBTF is under construction at the Consorzio RFX - Padova (I) premises, aimed at realizing the full scale prototype of the ITER N-NBI. Among other fundamental achievements (e.g. extracted current uniformity, efficient ion neutralization, long pulse duration), the success of the experimentation of the NBTF requires the achievement of a stable and easily obtained 1 MV voltage holding while negative ions are extracted and accelerated. The electrostatic configuration of the ITER and NBTF N-NBIs is extremely complex. It includes 5 main electrodes at high potential: five accelerating grids and a negative ion source, operating respectively at -0.2, -0.4, -0.6, -0.8, -1 MV with respect to the containing vessel. All electrodes have large surface (up to 10 m2 for the ion source, which constitutes the cathode); gap lengths are in the order of 100 mm between accelerating grids and a minimum of 980 mm for the -1 MV-to-ground gap. In such a peculiar situation, the full voltage attainment and holding is a key issue, being affected by Total Voltage Effect (TVE), Area Effect, residual gas pressure and electrode surface conditioning. This contribution aims to give an overview of the R&D so far carried out, in the Fusion Research Laboratories in particular the QST (formerly JAEA) lab in Naka, Ibaraki (Japan) , in the IRFM - CEA lab in Cadarache (France) and of the Italian Consorzio RFX lab in Padova. After a discussion of the present state-of-the-art about the voltage holding in the NBI accelerators, a description of the near future plan to achieve reliable voltage holding in the ITER N-NBI is given. The experiments will be performed in the labs of QST, RFX and, in a second stage, at the NBTF Facility in Padova. Finally, an example of spin-off of these researches is also given.

HV Holding in Vacuum, a Key Issue for the ITER Neutral Beam Injector

De Lorenzi A;
2018

Abstract

The achievement of burning plasma in ITER will require at least 33 MW of additional heating transferred to the plasma core by means of two 16.5 MW - 1 MeV injectors (N-NBI - Negative ion based - Neutral Beam Injector) of H or D atoms, with an extracted negative ion current of 40 A (i.e. 40 MW of extracted beam). A third Injector is foreseen as a future upgrade, to increase the power delivery to the ITER plasma up to 50 MW The N-NBI record so far obtained belongs to the Injector of JT60-U, in which have been extracted 17.4 A of negative current, accelerated up to 0.41 MeV. It is evident that the performances required for the ITER N-NBI exceed by far the present capability: for this reason, the Neutral Beam Test Facility - NBTF is under construction at the Consorzio RFX - Padova (I) premises, aimed at realizing the full scale prototype of the ITER N-NBI. Among other fundamental achievements (e.g. extracted current uniformity, efficient ion neutralization, long pulse duration), the success of the experimentation of the NBTF requires the achievement of a stable and easily obtained 1 MV voltage holding while negative ions are extracted and accelerated. The electrostatic configuration of the ITER and NBTF N-NBIs is extremely complex. It includes 5 main electrodes at high potential: five accelerating grids and a negative ion source, operating respectively at -0.2, -0.4, -0.6, -0.8, -1 MV with respect to the containing vessel. All electrodes have large surface (up to 10 m2 for the ion source, which constitutes the cathode); gap lengths are in the order of 100 mm between accelerating grids and a minimum of 980 mm for the -1 MV-to-ground gap. In such a peculiar situation, the full voltage attainment and holding is a key issue, being affected by Total Voltage Effect (TVE), Area Effect, residual gas pressure and electrode surface conditioning. This contribution aims to give an overview of the R&D so far carried out, in the Fusion Research Laboratories in particular the QST (formerly JAEA) lab in Naka, Ibaraki (Japan) , in the IRFM - CEA lab in Cadarache (France) and of the Italian Consorzio RFX lab in Padova. After a discussion of the present state-of-the-art about the voltage holding in the NBI accelerators, a description of the near future plan to achieve reliable voltage holding in the ITER N-NBI is given. The experiments will be performed in the labs of QST, RFX and, in a second stage, at the NBTF Facility in Padova. Finally, an example of spin-off of these researches is also given.
2018
Istituto gas ionizzati - IGI - Sede Padova
fusion reactors
neutral beam injector
voltage breakdown
File in questo prodotto:
Non ci sono file associati a questo prodotto.

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/346521
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
  • ???jsp.display-item.citation.isi??? ND
social impact