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

  • Author(s): Lazarus, EA
  • Navratil, GA
  • Greenfield, CM
  • Strait, EJ
  • Austin, ME
  • Burrell, KH
  • Casper, TA
  • Baker, DR
  • DeBoo, JC
  • Doyle, EJ
  • Durst, RD
  • Ferron, JR
  • Forest, CB
  • Gohil, P
  • Groebner, RJ
  • Heidbrink, WW
  • Hong, R
  • Howald, AW
  • Hsieh, C-L
  • Hyatt, AW
  • Jackson, GL
  • Kim, J
  • Lao, LL
  • Lanier, CJ
  • Leonard, AW
  • Lohr, JM
  • Haye, RJ La
  • Maingi, R
  • Miller, RL
  • Murakami, M
  • Osborne, TH
  • Perkins, LJ
  • Petty, CC
  • Rettig, CL
  • Rhodes, TL
  • Rice, BW
  • Sabbagh, SA
  • Schissel, DP
  • Scoville, JT
  • Snider, RT
  • Stallard, BW
  • Stambaugh, RD
  • John, HE St
  • Stockdale, RE
  • Taylor, PL
  • Taylor, TS
  • Thomas, DM
  • Turnbull, AD
  • Wade, MR
  • Wood, RD
  • Whye, DG
  • et al.
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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