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Status of the diagnostic development for the Tokamak Physics Experiment

S. S. Medley, W. A. Peebles, P. West, G. A. Wurden, G.H. Neilson

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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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What this paper is about

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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Available 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.

Key concepts: Divertor, Tokamak, Nuclear engineering, Physics, Superconducting magnet, Plasma, Bootstrap current, Toroid

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