Stellarator to fusion plasma confinement
The stellerator is a toroidal fusion plasma confinement device with nested magnetic flux surfaces, which offers the prospect of steady-state operation without plasma current. The required twist of the field lines is produced by external helical coils rather than by plasma current. The results achieved at Japanese and West German laboratories have made stellarator devices second only to tokamaks in progress toward fusion plasma conditions. The Advance Toroidal Facility (ATF) under construction at Oak Ridge National Laboratory and scheduled to operate in 1986 represents a significant advance. The ATF torsatron has been designed to operate steady state at high beta with good transport properties and to have sufficient flexibility to explore a wide variety of toroidal configurations, thereby contributing to the development of toroidal fusion reactors. 19 references, 3 figures.
- Research Organization:
- Oak Ridge National Lab., TN
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5762283
- Report Number(s):
- CONF-850301-
- Journal Information:
- Energy Technol. (Wash., D.C.); (United States), Journal Name: Energy Technol. (Wash., D.C.); (United States) Vol. 12; ISSN ENTED
- Country of Publication:
- United States
- Language:
- English
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700100* -- Fusion Energy-- Plasma Research
ANNULAR SPACE
ATF TORSATRON
CLOSED PLASMA DEVICES
CONFIGURATION
CONFINEMENT
ENGINEERING
PLASMA CONFINEMENT
RESEARCH PROGRAMS
SPACE
SPECIFICATIONS
STELLARATORS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOROIDAL CONFIGURATION
TORSATRON STELLARATOR