Initial results from the DIII-D tokamak
Conference
·
OSTI ID:7067764
The DIII-D tokamak was designed to exploit both (a) the strong dependence of limiting beta values and plasma energy confinement on high current, and (b) the effectiveness of the divertor configuration in obtaining good confinement. Initial operation of the device has resulted in ohmic confinement (tau approx. 150 ms) comparable to other large tokamaks and low levels of plasma impurities (Z/sub eff/ = 1.5 at anti n/sub e/ = 6 x 10/sup 19/ m/sup -3/). Both single null divertor and elongated dee-shaped limiter plasmas have been produced. This paper reports both attaining H-mode confinement during beam heating of plasmas in open divertor configurations and values of the Troyton scaling quantity (I/aB approx. 2) large enough to allow future studies of beta limits in regimes heretofore unattainable.
- Research Organization:
- General Atomics Co., San Diego, CA (USA); Japan Atomic Energy Research Inst., Tokyo; Oak Ridge National Lab., TN (USA); Lawrence Livermore National Lab., CA (USA); Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.); Commission of the European Communities, Abingdon (UK). JET Joint Undertaking
- DOE Contract Number:
- AC03-84ER51044
- OSTI ID:
- 7067764
- Report Number(s):
- GA-A-18683; CONF-861106-19; ON: DE87005861
- Country of Publication:
- United States
- Language:
- English
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