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Higher fusion power gain with profile control in DIII-D tokamak plasmas

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Published under licence by IOP Publishing Ltd
, , Citation E.A. Lazarus et al 1997 Nucl. Fusion 37 7 DOI 10.1088/0029-5515/37/1/I11

0029-5515/37/1/7

Abstract

Strong shaping, favourable for stability and improved energy confinement, together with a significant expansion of the central region of improved confinement in negative central magnetic shear target plasmas, increased the maximum fusion power produced in DIII-D by a factor of 3. Using deuterium plasmas, the highest fusion power gain, the ratio of fusion power to input power, Q, was 0.0015, corresponding to an equivalent Q of 0.32 in a deuterium-tritium plasma, which is similar to values achieved in tokamaks of larger size and magnetic field. A simple transformation relating Q to the stability parameters is presented

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10.1088/0029-5515/37/1/I11