Heating neutral beams for ITER: negative ion sources to tune fusion plasmas

Abstract

Neutral beam injection (NBI) based on a negative ion source is one of the basic heating and current drive systems designed for ITER required to reach its goals of the operation with high fusion power, P _fus ∼ 500 MW with fusion gain, Q = 10 for 400 s in a baseline scenario, and P _fus > 250 MW, Q = 5 operation for 3600 s in an advanced scenario. A total power of 33 MW from the two heating neutral beam (HNB) injectors is envisaged in the present scenario. The scope of the present paper is to provide an overview of the main aspects of the interaction of the HNBs with the ITER plasma. Various operational scenarios with different mixtures of the main ion species, He, H, DD and DT, foreseen at different phases of the ITER operation are considered.

Keywords

• neutral beams
• ITER plasmas
• L–H transition
• current drive
• plasma rotation