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Comparison of energy confinement in Doublet III limiter and divertor discharges with ohmic, neutral beam and electron cyclotron heating

Conference ·
OSTI ID:6431168
Scaling of total energy confinement time with line averaged density, toroidal field, plasma current and total input power is presented for vertically elongated tokamak plasmas, both limiter and divertor configurations, heated by Ohmic, neutral beam injection (NBI), and electron cyclotron heating (ECH) methods. Line averaged density plays no role in confinement in any type of discharge for densities above 2 x 10/sup 19/ m/sup -3/. Toroidal field affects confinement only in Ohmic divertor discharges. Current is the key variable in ECH and NBI discharges; Confinement time increases linearly with current. The similarity of the density and current scaling in NBI and ECH cases argues strongly that these scalings are properties of the auxiliary-heated plasmas in general and are not heating method specific results. Configuration also affects confinement: Expanded boundary divertor discharges show superior confinement for all three heating methods. Finally, the functional form of the variation of stored energy with input power in NBI discharges suggests that confinement time is approaching a new, power independent value at high input power.
Research Organization:
GA Technologies, Inc., San Diego, CA (USA)
DOE Contract Number:
AT03-84ER51044
OSTI ID:
6431168
Report Number(s):
GA-A-17694; CONF-840910-17; ON: DE85000449
Country of Publication:
United States
Language:
English