Spherical torus experiment (STX)

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:6072688

McManamy, T J; Lazarus, E A

The principal engineering features of the proposed Spherical Torus Experiment (STX) are described. Design is dominated by the small bore available for the ohmic heating (OH) solenoid and structural considerations for a situation in which B/sub p/ is approximately equal to B/sub t/. Unique features of a spherical torus plasma include large elongations without shaping fields; an exceptionally high ratio of plasma current to toroidal field, giving the potential for stability at very high beta; strong paramagnetism; and a variety of configurations, ranging from tokamak (q/sub a/) to revised-field pinch (RFP) (q/sub a/ < 1). Access to this regime requires aspect ratios less than 2. A feasibility study has been done for a beam-heated device with A = 1.67, R0 = 0.45, and K = 2. 3 refs., 9 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6072688
• Report Number(s): CONF-851102-42; ON: DE86003812; TRN: 86-005255
• Resource Relation: Conference: 11. symposium on engineering problems in fusion research, Austin, TX, USA, 18 Nov 1985
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SPHEROMAK DEVICES
DESIGN
COMPUTER-AIDED DESIGN
JOULE HEATING
MAGNETS
PRESSURE VESSELS
CLOSED PLASMA DEVICES
CONTAINERS
ELECTRIC HEATING
HEATING
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700200* - Fusion Energy- Fusion Power Plant Technology