Two heating neutral beam injectors on ITER will each contribute 16.5 MW of heating power to the plasma; space for a third has been reserved in the neutral beam cell of the Tokamak Building. (A smaller neutral beam—the diagnostic neutral beam—will probe the plasma to provide information on the helium ash density produced by the D-T fusion reactions in the fusion plasma.)
ITER's heating neutral beam injectors will shoot uncharged high-energy particles into the plasma where, by way of chaotic motion and collision, they will transfer their energy to the charged plasma particles.
In the injector, a beam source generates electrically charged deuterium ions that are accelerated through a succession of grids to a kinetic energy of 1 Mega electron Volt (MeV). A "neutralizer" rips them of their electrical charges, allowing them to penetrate the tokamak's magnetic cage and, by way of multiple collisions with the particles inside the plasma, raise plasma temperature.
The large plasma volume at ITER has imposed new requirements on this proven method of injection: the particles will have to move three to four times faster than in previous systems in order to penetrate far enough into the plasma, and at these higher rates the positively charged ions become difficult to neutralize. At ITER, for the first time, a negatively charged ion source has been selected to circumvent this problem. Although the negative ions will be easier to neutralize, they will also be more challenging to create and to handle than positive ions. The additional electron that gives the ion its negative charge is only loosely bound, and consequently readily lost.
A test program is underway now at the ITER Neutral Beam Test Facility in Padua, Italy to investigate challenging physics and technology issues of neutral beam injection in advance of the installation of the heating neutral beam equipment at ITER. More on the ITER Neutral Beam Test Facility
here.