Status of the diagnostic development for the Tokamak Physics Experiment
S. S. Medley, W. A. Peebles, P. West, G. A. Wurden, G.H. Neilson
Abstract
S. S. Medley, W. A. Peebles, P. West, G. A. Wurden, G.H. Neilson
Abstract
Summary form only given. A superconducting tokamak physics experiment (TPX) is being designed by an integrated US national team to develop and demonstrate optimized steady-state operation of a tokamak device. Key physics features such as strong shaping, a double-null poloidal divertor, full noninductive current drive, and current profile control capability will be used to explore improvements in energy confinement and beta limit scaling in high-aspect-ratio plasmas with a high bootstrap current fraction. Steady-state operation of TPX permits these studies to be extended to time scales significantly exceeding the global current-relaxation time and the plasma-wall equilibration time. The TPX program will contribute to the development of key technologies required for fusion power reactors such as superconducting toroidal and poloidal magnet systems, high-heat-flux actively cooled divertor and first wall systems, and in-vessel remote maintenance.
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Summary form only given. A superconducting tokamak physics experiment (TPX) is being designed by an integrated US national team to develop and demonstrate optimized steady-state operation of a tokamak device. Key physics features such as strong shaping, a double-null poloidal divertor, full noninductive current drive, and current profile control capability will be used to explore improvements in energy confinement and beta limit scaling in high-aspect-ratio plasmas with a high bootstrap current fraction. Steady-state operation of TPX permits these studies to be extended to time scales significantly exceeding the global current-relaxation time and the plasma-wall equilibration time. The TPX program will contribute to the development of key technologies required for fusion power reactors such as superconducting toroidal and poloidal magnet systems, high-heat-flux actively cooled divertor and first wall systems, and in-vessel remote maintenance.
Key concepts: Divertor, Tokamak, Nuclear engineering, Physics, Superconducting magnet, Plasma, Bootstrap current, Toroid