Review of Instrumentation and control in the neutral beam test facility

The ITER Project is an international collaboration under construction in southern France to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The heating neutral beam injectors are ITER additional heating systems that are needed to achieve the ITER plasma high-confinement regime. The neutral beam test facility is an R&D program established by ITER the purpose of which is to provide a true reliable neutral beam injector for ITER, able to achieve full performance (16.5 MW, 3600 s beam on time). Two experiments are under construction at the neutral beam test facility, namely SPIDER, the ITER full-size ion source, and MITICA the full prototype of the ITER heating neutral beam injector. The paper, after describing the neutral beam test facility, will focus on the instrumentation and control aspects of the SPIDER and MITICA experiments.