The Cadarache Negative Ion Experiments
SOFE '95 - 16TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2: SEEKING A NEW ENERGY ERA(1995)
Abstract
Up to energies of 140 keV neutral beam injection (NBI) based on positive ions has proven to be a reliable and flexible plasma heating method and has provided major contributions to most of the important experiments on virtually all large tokamaks around the world. As a candidate for additional heating and current drive on next step fusion machines (ITER) it is hoped that NBI can be equally successful. The ITER NBI parameters of 1 MeV 50 MW D0 demand primary D- beams with current densities of at least 15 mA/cm2. Although considerable progress has been made in the area of negative ion production and acceleration the high demands still require substantial and urgent development
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Key words
current density
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