Nuclear Fusion · 1999 · 191 citations · 147 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringHeat TransferPlasma PhysicsCurrent DriveFusion PlasmasHigh-temperature PlasmasNeutral Beam InjectionPlasma HeatingPlasma WavesAuxiliary HeatingAuxiliary Heating SystemsCurrent Drive SystemsIon Cyclotron WavesLower Hybrid WavesPlasma Heating SystemsPlasma Start-upWall Conditioning
Heating and current drive systems in ITER must provide heating for H‑mode transition and ignition, plasma burn control, steady‑state current drive and profile control, MHD stability, start‑up assistance, and wall conditioning, yet no single system can meet all these flexible requirements. The paper reviews the physics of ITER heating and current drive systems, discusses experimental results, outlines key application aspects, and summarizes required technological developments. The study evaluates four candidate systems—170 GHz electron cyclotron, 40–70 MHz fast waves, 5 GHz lower hybrid, and 1 MeV negative‑ion neutral beam injection—selected for their physics maturity, experimental heritage, and feasibility for ITER. Key application aspects for ITER and the major technological developments needed for each heating system are identified.
Heating and current drive systems must fulfil several roles in ITER operating scenarios: heating through the H-mode transition and to ignition; plasma burn control; current drive and current profile control in steady state scenarios; and control of MHD instabilities. They must also perform ancillary functions, such as assisting plasma start-up and wall conditioning. It is recognized that no one system can satisfy all of these requirements with the degree of flexibility that ITER will require. Four heating and current drive systems are therefore under consideration for ITER: electron cyclotron waves at a principal frequency of 170GHz; fast waves operating in the range 40-70MHz (ion cyclotron waves); lower hybrid waves at 5GHz; and neutral beam injection using negative ion beam technology for operation at 1MeV energy. It is likely that several of these systems will be employed in parallel. The systems have been chosen on the basis of the maturity of physics understanding and operating experience in current experiments and on the feasibility of applying the relevant technology to ITER. Here, the fundamental physics describing the interaction of these heating systems with the plasma is reviewed, the relevant experimental results in the exploitation of the heating and current drive capabilities of each system are discussed, key aspects of their application to ITER are outlined, and the major technological developments required in each area are summarized.
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Plasma Physics and Controlled Nuclear Fusion Research
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