Design of neutral beam system for ITER-FEAT

Inoue, Takashi; Pietro, E. Di; Hanada, M.; Hemsworth, R.; Krylov, A.; Kulygin, V. M.; Massmann, P.; Mondino, P.L.; Okumura, Y.; Panasenkov, A. A.; Speth, E.; Watanabe, K.

doi:10.1016/s0920-3796(01)00339-8

Cited by 64 publications

(43 citation statements)

References 2 publications

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“…Neutral beam injectors in all large tokamaks are based on a similar beamline structure: an ion source connected to an electrostatic accelerator is followed by a neutralizer and a residual ion dump [16]. BBNBI follows the neutral particles starting from the grounded grid, i.e., the last accelerator grid.…”

Section: Describing the Injector Geometrymentioning

confidence: 99%

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Asunta

Govenius

Budny

et al. 2015

Computer Physics Communications

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Neutral beam injection (NBI) will be one of the main sources of heating and non-inductive current drive in ITER. Due to high level of injected power the beam induced heat loads present a potential threat to the integrity of the first wall of the device, particularly in the presence of non-axisymmetric perturbations of the magnetic field. Neutral beam injection can also destabilize Alfvén eigenmodes and energetic particle modes, and act as a source of plasma rotation. Therefore, reliable and accurate simulation of NBI is important for making predictions for ITER, as well as for any other current or future fusion device. This paper introduces a new beamlet-based neutral beam ionization model called BBNBI. It takes into account the fine structure of the injector, follows the injected neutrals until ionization, and generates a source ensemble of ionized NBI test particles for slowing down calculations. BBNBI can be used as a stand-alone model but together with the particle following code ASCOT it forms a complete and sophisticated tool for simulating neutral beam injection. The test particle ensembles from BBNBI are found to agree well with those produced by PENCIL for JET, and those produced by NUBEAM both for JET and ASDEX Upgrade plasmas. The first comprehensive comparisons of beam slowing down profiles of interest from BBNBI+ASCOT with results from PENCIL and NUBEAM/TRANSP, for both JET and AUG, are presented. It is shown that, for an axisymmetric plasma, BBNBI+ASCOT and NUBEAM agree remarkably well. Together with earlier 3D studies, these results further validate using BBNBI+ASCOT also for studying phenomena that require particle following in a truly three-dimensional geometry.

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Section: Describing the Injector Geometrymentioning

confidence: 99%

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Asunta

Govenius

Budny

et al. 2015

Computer Physics Communications

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“…In the ITER NB beamline 4-channels design has been adopted [11] in favor of 2-or 3-channel solutions accounting additional considerations like lower power density onto the RID plates, lower defl ection voltage between its plates and voltage symmetry in the RID (outer and central panels are at ground potential, while other two are at -23 kV).…”

Section: Short Beamline Design and Beam Transmissionmentioning

confidence: 99%

NBI: Progress in Physics and Engineering toward Fusion Reactors: 4. ITER NB System: Compact Beamline and Design against Radiation

Krylov

Inoue

2005

J. Plasma Fusion Res.

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The present ITER NB system includes two design features: short beamline design and vacuum insulated beam source (ion source and accelerator) which sustain 1 MV high voltage under radiation environment. The short beamline design is achieved by subdividing interior of the neutraliser into narrow channels to reduce gas conductance, and hence, the gas fl ow rate to ensure target thickness required for neutralisation. Optimizing the beam transmission and reionisation loss of neutral beams, the axial length of the ITER NB injector was shortened to be 23.4 m with a reasonably high injection effi ciency. Three-dimensional neutron transport analyses clarifi ed possible excess power dissipation due to radiation-induced conductivity, if the high voltage is insulated by conventional gas such as SF 6 . Thus, design of vacuum insulated beam source has been established for the present ITER NB system.

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“…SPIDER (Source for Production of Ions of Deuterium Extracted from RF plasma) is a full-size test-bed of the ion source and extractor for the Heating Neutral Beam injectors (HNB), which will be used for additional heating of the ITER tokamak [1]. MITICA (Megavolt ITER Injector Concept Advancement) is a complete prototype of the ITER HNB.…”

Section: Introductionmentioning

confidence: 99%

Improvements of the magnetic field design for SPIDER and MITICA negative ion beam sources

Chitarin

Agostinetti²,

Aprile³

et al. 2015

AIP Conference Proceedings

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Design of neutral beam system for ITER-FEAT

Cited by 64 publications

References 2 publications

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

NBI: Progress in Physics and Engineering toward Fusion Reactors: 4. ITER NB System: Compact Beamline and Design against Radiation

Improvements of the magnetic field design for SPIDER and MITICA negative ion beam sources

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