A 160‐keV neutral deuterium beam injector has been developed for plasma heating in JET
(Joint European Torus) fusion experiment. This injector has been reliably operated at 5.9 …

The design of a new type of neutral beam injector that recovers the energy of the
unneutralized part of the beam, developed at Cadarache Laboratory, is presented. The …

Since 1987, the DIII-D tokamak has utilized up to eight neutral beam ion sources on four
beamlines for plasma heating and current drive. Extending the beam system capability will …

Neutral beam injector for EAST is designed to deliver deuterium beams with a power of 2
MW to 4 MW at an energy of 50 keV to 80 keV into the plasma with a beam dimension of 12 …

The objective of linear IFMIF prototype accelerator is to demonstrate 125 mA/CW deuterium
ion beam acceleration up to 9 MeV. The injector has been developed in CEA Saclay and …

The injector for the Fusion Materials Irradiation Test (FMIT) Facility has been designed to
deliver a 100-keV, 125-mA dc deuteron beam. A prototype injector has been built to run with …

A new deuterium pellet injector intended for maintaining a steady-state fusion reaction in a
plasma is described. A technique for producing pellets by continuous solid deuterium …

A prototype neutral beam injector unit for JT-60 has been constructed prior to fabrication of
14 injector units for JT-60 to confirm system performances of a beam line and a power …

The TCV tokamak contributes to physics understanding in fusion reactor research by
harnessing a wide experimental tool set: in particular flexible shaping and high power …

In the framework of the IFMIF-EVEDA project (International Fusion Materials Irradiation
Facility-Engineering Validation and Engineering Design Activities), CEA/IRFU is in charge of …