Recent improvements to the ITER neutral beam system design

L.R. Grisham, P. Agostinetti, G. Barrera, P. Blatchford, D. Boilson, J. Chareyre, G. Chitarin, H.P.L. De Esch, A. De Lorenzi, P. Franzen, U. Fantz, M. Gagliardi, R.S. Hemsworth, M. Kashiwagi, D. King, A. Krylov, M. Kuriyama, N. Marconato, D. Marcuzzi, M. RoccellaL. Rios, A. Panasenkov, N. Pilan, M. Pavei, A. Rizzolo, E. Sartori, G. Serianni, P. Sonato, V. Pilard, M. Tanaka, H. Tobari, P. Veltri, P. Zaccaria

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Abstract

The ITER [1] fusion device is expected to demonstrate the feasibility of magnetically confined deuterium-tritium plasma as an energy source which might one day lead to practical power plants. Injection of energetic beams of neutral atoms (up to 1 MeV D0or up to 870 keV H0) will be one of the primary methods used for heating the plasma, and for driving toroidal electrical current within it, the latter being essential in producing the required magnetic confinement field configuration. The design calls for each beamline to inject up to 16.5 MW of power through the duct into the tokamak, with an initial complement of two beamlines injecting parallel to the direction of the current arising from the tokamak transformer effect, and with the possibility of eventually adding a third beamline, also in the co-current direction. The general design of the beamlines has taken shape over the past 17 years [2], and is now predicated upon an RF-driven negative ion source based upon the line of sources developed by the Institute for Plasma Physics (IPP) at Garching during recent decades [3-5], and a multiple-aperture multiple-grid electrostatic accelerator derived from negative ion accelerators developed by the Japan Atomic Energy Agency (JAEA) across a similar span of time [6-8]. During the past years, the basic concept of the beam system has been further refined and developed, and assessment of suitable fabrication techniques has begun. While many design details which will be important to the installation and implementation of the ITER beams have been worked out during this time, this paper focuses upon those changes to the overall design concept which might be of general interest within the technical community.
Original languageEnglish
Pages (from-to)1805 - 1815
Number of pages11
JournalFusion Engineering and Design
Volume87
Issue number11
DOIs
Publication statusPublished - Nov 2012
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Grisham, L. R., Agostinetti, P., Barrera, G., Blatchford, P., Boilson, D., Chareyre, J., Chitarin, G., De Esch, H. P. L., De Lorenzi, A., Franzen, P., Fantz, U., Gagliardi, M., Hemsworth, R. S., Kashiwagi, M., King, D., Krylov, A., Kuriyama, M., Marconato, N., Marcuzzi, D., ... Zaccaria, P. (2012). Recent improvements to the ITER neutral beam system design. Fusion Engineering and Design, 87(11), 1805 - 1815. https://doi.org/10.1016/j.fusengdes.2012.08.001