Advanced tokamak reactors based on the spherical torus (ATR/ST). Preliminary design considerations

Technical Report · Sun Jun 01 00:00:00 EDT 1986

DOI:https://doi.org/10.2172/5677294· OSTI ID:5677294

Miller, R L; Krakowski, R A; Bathke, C G; Copenhaver, C; Schnurr, N M; Engelhardt, A G; Seed, T J; Zubrin, R M

Preliminary design results relating to an advanced magnetic fusion reactor concept based on the high-beta, low-aspect-ratio, spherical-torus tokamak are summarized. The concept includes resistive (demountable) toroidal-field coils, magnetic-divertor impurity control, oscillating-field current drive, and a flowing liquid-metal breeding blanket. Results of parametric tradeoff studies, plasma engineering modeling, fusion-power-core mechanical design, neutronics analyses, and blanket thermalhydraulics studies are described. The approach, models, and interim results described here provide a basis for a more detailed design. Key issues quantified for the spherical-torus reactor center on the need for an efficient drive for this high-current (approx.40 MA) device as well as the economic desirability to increase the net electrical power from the nominal 500-MWe(net) value adopted for the baseline system. Although a direct extension of present tokamak scaling, the stablity and transport of this high-beta (approx.0.3) plasma is a key unknown that is resoluble only by experiment. The spherical torus generally provides a route to improved tokamak reactors as measured by considerably simplified coil technology in a configuration that allows a realistic magnetic divertor design, both leading to increased mass power density and reduced cost.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5677294
• Report Number(s): LA-10740-MS; ON: DE86013627
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TOKAMAK TYPE REACTORS
DESIGN
ASPECT RATIO
CURRENT-DRIVE HEATING
DIVERTORS
HIGH-BETA PLASMA
MAGNET COILS
SPHERICAL CONFIGURATION
CONFIGURATION
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
EQUIPMENT
HEATING
JOULE HEATING
PLASMA
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology