Answers are grounded in this paper and cite their sources.
ITER is planned to be the first fusion experiment operating under reactor-relevant conditions. The following requirements are given: ITER should (1) achieve extended burn in inductively driven plasma at Q ⩾ 10, whilst not precluding the possibility of controlled ignition, (2) aim at demonstrating steady-state operation using non-inductive current drive at Q ⩾ 5, (3) demonstrate availability and integration of essential fusion technologies, and (4) test components for a future reactor including tritium breeding module concepts, with the 14 MeV neutron power load on the first wall ⩾ 0.5 MW m -2 and fluence ⩾ 0.3 MW am -2 . The ITER tokamak is designed not only to satisfy these requirements but also to have flexibility of plasma operations. This flexibility will provide a wide range of opportunities to develop inductive and non-inductive reactor core plasmas and to study burning plasma physics. Possible operational modes studying physics and technical issues of burning plasmas are overviewed.
No takes yet. Share an insight, caveat, or question.
Shimomura et al. (2001) studied this question.
Synapse has enriched 10 related papers. Consider them for comparative context: