Experimental exploration of profile control in the Princeton Beta Experiment-Modified (PBX-M) tokamak

Technical Report · Sat May 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/6422961· OSTI ID:6422961

Bernabei, S; Bell, R; Chance, M; Chu, T K; Corneliussen, M; Davis, W; Gettelfinger, G; Gibney, T; Greenough, N; Hatcher, R; Hermann, H; Ignat, D; Jardin, S; Kaita, R; Kaye, S; Kessel, C; Kozub, T; Hugel, H; Lagin, L; LeBlanc, B ; Manickam, J; Okabayashi, M; Oliver, H; Ono, M; Paul, S; Preische, S; Roney, P; Sauthoff, N; Schweitzer, S; Sesnic, S; Sun, Y; Takahashi, H; Tighe, W; Valeo, E

The experimental program of the Princeton Beta Experiment-Modified (PBX-M) Tokamak is directed towards tailoring plasma profiles to achieve greater stability and confinement and to gain access to the second stability region. Modification of the current density profile has been achieved with lower hybrid current drive (LHCD), leading to a regime free of global magnetohydrodynamic modes, while raising the value of q(O) above unity. The diffusion of the fast electrons produced by LHCD has been examined using two dimensional hard x-ray imaging. Ion Bernstein waves (IBW) have been used for ion heating: a preliminary analysis shows that ion heating was spatially localized and in agreement with theoretical calculations. Divertor biasing has modified the electric field inside the last closed surface, resulting in the formation of a transport barrier, which in turn has reduced the threshold power of Neutral Beam Injection (NBI) for H-mode transition by 25%.

• Research Organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 6422961
• Report Number(s): PPPL-2905; ON: DE93014818
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPACT IGNITION TOKAMAK
CURRENT DENSITY
PLASMA HEATING
BERNSTEIN MODE
DIFFUSION
DIVERTORS
ELECTRIC FIELDS
H-MODE PLASMA CONFINEMENT
LOWER HYBRID CURRENT DRIVE
MHD EQUILIBRIUM
NEUTRAL ATOM BEAM INJECTION
PARAMETRIC INSTABILITIES
BEAM INJECTION
CLOSED PLASMA DEVICES
CONFINEMENT
EQUILIBRIUM
HEATING
INSTABILITY
NON-INDUCTIVE CURRENT DRIVE
OSCILLATION MODES
PLASMA CONFINEMENT
PLASMA INSTABILITY
PLASMA MACROINSTABILITIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
700350* - Plasma Production
Heating
Current Drive
& Interactions- (1992-)