Plasma Physics and Controlled Fusion · 2001 · 67 citations · 4 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringNuclear PhysicsPlasma PhysicsCurrent DriveFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionNuclear FusionPlasma ConfinementBurning Plasma PhysicsNon-inductive Current DriveReactor Core PhysicsSteady-state OperationSteady-state Tokamak OperationTokamak PhysicsTokamak PlasmasTritium Breeding Systems
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.
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Y. Shimomura, R. Aymar, V.A. Chuyanov et al. · Nuclear Fusion · 2001 · 130 citations
Prospects of a stationary tokamak reactor
M. Kikuchi · Plasma Physics and Controlled Fusion · 1993 · 67 citations
How far is a fusion power reactor from an experimental reactor
R. Toschi, P. Barabaschi, D. Campbell et al. · Fusion Engineering and Design · 2001 · 33 citations