To deliver power to the fusion plasma in ITER, two heating
neutral beam injectors will be installed. They are designed to provide the power of 17MW each, through the 23m beamlines, up to the four-meter diameter container: in order to deposit sufficient heating power in the plasma core instead of the plasma edges, the beam particle energy shall be about 1MeV, thus increasing the neutral beam system complexity to an unprecedented level. This will be the main auxiliary heating system of the reactor. Due to its low conversion efficiency, the neutral beam injector first needs to start a precursor negative ion beam of 40A, and then neutralizes it by passing it through a gas cell (with an efficiency <60%), and then by a residual ion dump (the remaining 40—20% negative, 20% positive). The neutralized beam is then dumped on a
calorimeter during conditioning phases, or coupled with the plasma. Further reionization losses or interception with the mechanical components reduce its current to 17A.