Tokamak power systems studies: A second stability power reactor
A number of innovative physics and engineering features have been studied which promise to greatly improve the reactor prospects of tokamaks relative to STARFIRE. A reference design point has been developed with the following features: large aspect ratio (A = 6); high beta (..beta.. approx. = 0.20), with only mild shaping and no indentation, which brings the maximum toroidal field down to 7 T; low toroidal current (I approx. = 5MA), which reduces the cost of the current drive and EF coil system; and steady-state operation with combined fast wave and lower hybrid wave current drive. The key to high beta operation with low toroidal current lies in utilizing second stability regime equilibria with control of the current achieved by the appropriate choice of wave frequencies and spectra. By selecting an axial safety factor q(o) = 2.0, MHD stability has been found above ..beta.. approx. = 0.20. Additional features include: impurity control with self-pumped limiters which bury helium on continuously deposited metal surfaces; liquid Li-cooled blanket which provides good performance with low pressure operation; vanadium alloy blanket structure for higher thermal efficiency (eta = 0.42), longer lifetime and reduced activation; and reduced reactor mass (higher power density) due to smaller TF coil, less shielding, fewer blanket penetrations, and higher wall loading. At low neutron wall loads this device represents a minimum capital cost unit. However, economies of scale are strong, and eventually higher wall loads (W approx. = 8 MW/m/sup 2/, P/sub net/ = 1400 MW) may prove most attractive. Preliminary investigations show inherently safe operation is likely at W greater than or equal to 5 MW/m/sup 2/. 15 refs., 3 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5607665
- Report Number(s):
- CONF-871007-73; ON: DE88002890
- Resource Relation:
- Conference: 12. symposium on fusion engineering, Monterey, CA, USA, 12 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TOKAMAK TYPE REACTORS
DESIGN
ASPECT RATIO
COST
FIRST WALL
IMPURITIES
LITHIUM
LOWER HYBRID HEATING
MAGNETIC FIELDS
MHD EQUILIBRIUM
POWER SYSTEMS
PUMPED LIMITERS
SAFETY
STABILITY
STEADY-STATE CONDITIONS
WALL LOADING
ALKALI METALS
ELEMENTS
ENERGY SYSTEMS
EQUILIBRIUM
HEATING
HIGH-FREQUENCY HEATING
LIMITERS
METALS
PLASMA HEATING
POWER DENSITY
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology