H-modes studies in PDX

Conference · Sun Jul 01 04:00:00 EDT 1984

OSTI ID:6713749

Fonck, R J; Beirsdorfer, P; Bell, M; Bol, K; Boyd, D; Buchenauer, D; Budny, R; Cavallo, A; Couture, P; Crowley, T

A regime of enhanced energy confinement during neutral beam heating has been obtained routinely in the PDX tokamak after modifications to form a closed divertor geometry. Plasma density profiles were broad and the electron temperature at the plasma edge reached values of approx. 400 eV in the H-mode phase of a discharge. A comparison of closed divertor discharges with moderate and intense gas puffing indicates that a requirement for obtaining high confinement times is the localization of the plasma fueling source in the divertor throat region. While high confinement was attained at moderate injected powers (P/sub INJ/ less than or equal to 3 MW), confinement was degraded at higher powers due to both increased edge instabilities and, especially, the intense gas puffing needed to prevent disruptions. Initial results with a particle scoop limiter indicate high particle confinement times and energy confinement times approaching those of diverted H-mode plasmas.

• Research Organization: Princeton Univ., NJ (USA). Plasma Physics Lab.
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 6713749
• Report Number(s): PPPL-2118; CONF-840311-14; ON: DE84015148
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101* -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
BEAM INJECTION
CLOSED PLASMA DEVICES
CONFINEMENT
FLUID INJECTION
GAS INJECTION
NEUTRAL ATOM BEAM INJECTION
PDX DEVICES
PLASMA CONFINEMENT
PLASMA DENSITY
REACTOR FUELING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES