Abstract

Neutral beam injection, for plasma heating, will supposedly be achieved, in ITER, by collisional detachment of a pre-accelerated D − beam. Collisional detachment, however, makes use of a D 2 -filled neutralisation chamber, which has severe drawbacks, including the necessity to set the D − -ion source at −1 MV. Photodetachment, in contradistinction, would have several advantages as a neutralisation method, including the absence of gas injection, and the possibility to set the ion source close to the earth potential. Photodetachment, however, requires a very high laser flux. The presented work has consisted in implementing an optical cavity, with a finesse greater than 3000, to make such a high illumination possible with a state-of-the-art CW (continuous-wave) laser. A 1.2 keV 1 H − -beam (only 20 times slower than the 1 MeV 2 D − ion beams to be prepared for ITER) was photodetached with more-than-50% efficiency, with only 24 W of CW laser input. This experimental demonstration paves the way for developing real-size photoneutralizers, based on the implementation of refolded optical cavities around the ion beams of neutral beam injectors. Depending on whether the specifications of the laser power or the cavity finesse will be more difficult to achieve in real scale, different architectures can be considered, with greater or smaller numbers of optical refoldings or (inclusively) optical cavities in succession, on the beam to be neutralised.

Highlights

  • The history of fast D0 neutral beam generation for plasma heating has followed three technical ways in succession

  • We have shown that optical-cavity enhancement can make photodetachment an actual means of neutralizing the greater part of a H− beam, and produce a neutral beam efficiently

  • Up-scaling remains to be done as concerns the beam diameter and ion velocity, but the demonstration already dealt with cavity finesses of the order of magnitude to be met in real-size neutral beam injectors

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Summary

Introduction

The history of fast D0 neutral beam generation for plasma heating has followed three technical ways in succession. Electron capture by accelerated D+ ion was historically the first one. Collisional detachment of accelerated D− ions was developed to overcome the decrease of electron-capture probability at higher acceleration voltages. It is the procedure implemented on ITER, but with a limited efficiency that will probably not be sustainable for industrial developments. Photodetachment of accelerated D− ions has been considered since the 1980s as a very promising technique [1]. Namely the circa 1 eV energy of every absorbed photon, is very low when compared to the 1 MeV kinetic energy of every produced neutral atom. Photons are insensitive to electric fields, and the photodetachment zone does not need any gas input, which makes

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