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Higher Fusion Power Gain with Current and Pressure Profile Control in Strongly Shaped 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, R
  • Ferron, JR
  • Forest, CB
  • Gohil, P
  • Groebner, RJ
  • Heidbrink, WW
  • Hong, R
  • Houlberg, WA
  • Howald, AW
  • Hsieh, C
  • Hyatt, AW
  • Jackson, GL
  • Kim, J
  • Lao, LL
  • Lasnier, CJ
  • Leonard, AW
  • Lohr, J
  • La Haye RJ
  • 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
  • Staebler, GM
  • Stallard, BW
  • Stambaugh, RD
  • St John HE
  • Stockdale, RE
  • Taylor, PL
  • Thomas, DM
  • Turnbull, AD
  • Wade, MR
  • Wood, R
  • Whyte, D
  • et al.

Fusion power has been increased by a factor of 3 in DIII-D by tailoring the pressure profile to avoid the kink instability in H-mode plasmas. The resulting plasmas are found to have neoclassical ion confinement. This reduction in transport losses in beam-heated plasmas with negative central shear is correlated with a dramatic reduction in density fluctuations. Improved magnetohydrodynamic stability is achieved by controlling the plasma pressure profile width. In deuterium plasmas the highest gain Q (the ratio of fusion power to input power), was 0.0015, corresponding to an equivalent Q of 0.32 in a deuterium-tritium plasma. © 1996 The American Physical Society.

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