- Main
Higher Fusion Power Gain with Current and Pressure Profile Control in Strongly Shaped DIII-D Tokamak Plasmas
- 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-M;
- Houlberg, WA;
- Howald, AW;
- Hsieh, C-L;
- 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.
Abstract
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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