LONG-PULSE, HIGH-PERFORMANCE DISCHARGES IN THE DIII-D TOKAMAK

Significant progress in obtaining high performance discharges for many energy confinement times in the DIII-D tokamak has been realized since the previous IAEA meeting. In relation to previous discharges, normalized performance {approx}10 has been sustained for >5 {tau}{sub E} with q{sub min} >1.5. (The normalized performance is measured by the product {beta}{sub N} H{sub 89} indicating the proximity to the conventional {beta} limits and energy confinement quality, respectively.) These H-mode discharges have an ELMing edge and {beta} {approx}{le} 5%. The limit to increasing {beta} is a resistive wall mode, rather than the tearing modes previously observed. Confinement remains good despite the increase in q. The global parameters were chosen to optimize the potential for fully non-inductive current sustainment at high performance, which is a key program goal for the DIII-D facility in the next two years. Measurement of the current density and loop voltage profiles indicate {approx}75% of the current in the present discharges is sustained non-inductively. The remaining ohmic current is localized near the half radius. The electron cyclotron heating system is being upgraded to replace this remaining current with ECCD. Density and {beta} control, which are essential for operating advanced tokamak discharges, were demonstrated in ELMing H-mode discharges with {beta}{sub N}H{sub 89} {approx} 7 for up to 6.3 s or {approx} 34 {tau}{sub E}. These discharges appear to be in resistive equilibrium with q{sub min} {approx} 1.05, in agreement with the current profile relaxation time of 1.8 s.

[1]  T. Petrie,et al.  Initial performance results of the DIII-D Divertor 2000 , 2001 .

[2]  E. D. Fredrickson,et al.  Control of the resistive wall mode in advanced tokamak plasmas on DIII-D , 2000 .

[3]  L. Lao,et al.  Modification of high mode pedestal instabilities in the DIII-D tokamak , 2000 .

[4]  E. J. Strait,et al.  Increasing the beta limit due to neoclassical tearing modes by raising the axial safety factor q(0) > 1 , 2000 .

[5]  C. G. Gimblett,et al.  Torque balance and rotational stabilization of the resistive wall mode , 2000 .

[6]  D. J. Campbell,et al.  Chapter 1: Overview and summary , 1999 .

[7]  O. Sauter,et al.  Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime , 1999 .

[8]  W. Kerner,et al.  Plasma confinement in JET H?mode plasmas with H, D, DT and T isotopes , 1999 .

[9]  T. C. Luce,et al.  Scaling of heat transport with collisionality , 1999 .

[10]  L. Lao,et al.  PROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIII-D , 1998 .

[11]  Robert L. Miller,et al.  Synergism between cross-section and profile shaping in beta optimization of tokamak equilibria with negative central shear , 1998 .

[12]  L. L. Lao,et al.  Real time equilibrium reconstruction for tokamak discharge control , 1998 .

[13]  Robert Dewar,et al.  Theory and simulation of rotational shear stabilization of turbulence , 1998 .

[14]  T. C. Luce,et al.  Experimental constraints on transport from dimensionless parameter scaling studies , 1998 .

[15]  L. L. Lao,et al.  Direct Measurement of the Radial Electric Field in Tokamak Plasmas using the Stark Effect , 1997 .

[16]  L. L. Lao,et al.  Beta limits in long-pulse tokamak discharges , 1997 .

[17]  Robert L. Miller,et al.  Stability of negative central magnetic shear discharges in the DIII-D tokamak , 1997 .

[18]  Hong,et al.  Higher Fusion Power Gain with Current and Pressure Profile Control in Strongly Shaped DIII-D Tokamak Plasmas. , 1996, Physical review letters.

[19]  L. L. Lao,et al.  Rotational and magnetic shear stabilization of magnetohydrodynamic modes and turbulence in DIII‐D high performance discharges , 1996 .

[20]  M. Mauel,et al.  The formation and evolution of negative central magnetic shear current profiles on DIII-D , 1996 .

[21]  Turnbull,et al.  High Beta and Enhanced Confinement in a Second Stable Core VH-Mode Advanced Tokamak. , 1995, Physical review letters.

[22]  Lao,et al.  Determination of the noninductive current profile in tokamak plasmas. , 1994, Physical review letters.

[23]  E. J. Strait,et al.  Stability of high beta tokamak plasmas , 1994 .

[24]  Bondeson,et al.  Stabilization of external modes in tokamaks by resistive walls and plasma rotation. , 1994, Physical review letters.

[25]  Manickam,et al.  Improved plasma performance in tokamaks with negative magnetic shear. , 1994, Physical review letters.

[26]  G. L. Campbell,et al.  Design and operation of the multipulse Thomson scattering diagnostic on DIII‐D (invited) , 1992 .

[27]  L. Lao,et al.  An optimization of beta in the DIII-D tokamak , 1992 .

[28]  L. L. Lao,et al.  Equilibrium analysis of current profiles in tokamaks , 1990 .

[29]  D. Post,et al.  ITER: Physics basis , 1990, 1990 Plasma Science IEEE Conference Record - Abstracts.

[30]  Tadashi Sekiguchi,et al.  Plasma Physics and Controlled Nuclear Fusion Research , 1987 .

[31]  F. Wagner,et al.  Experimental evidence for neoclassical ion transport effects in the H-transition of ASDEX , 1985 .

[32]  J. L. Luxon,et al.  Big Dee - A Flexible Facility Operating Near Breakeven Conditions , 1985 .

[33]  T. Stringer MHD problems relevant to jet , 1981 .

[34]  B. Coppi Physics of plasmas close to thermonuclear conditions: Proceedings of the course held in Varenna, Italy 27 August--8 September 1979 , 1981 .

[35]  F. Hinton,et al.  Theory of plasma transport in toroidal confinement systems , 1976 .

[36]  J. W. Connor,et al.  Diffusion Driven Plasma Currents and Bootstrap Tokamak , 1971 .