Vertical stability requirements for ARIES-I reactor

Conference · Sun Jan 01 00:00:00 EST 1989

DOI:https://doi.org/10.1109/FUSION.1989.102365· OSTI ID:5393957

Bathke, C G; Jardin, S C; Leuer, J A; Ward, D J ^[1]

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1. Los Alamos National Lab., NM (USA)

The vertical stability of the ARIES-I reactor design is analyzed with the NOVA-W, PSTAB, and TSC codes. A growth rate of {approximately}5.7 s{sup -1} is predicted for a vacuum vessel positioned behind the scrapeoff, first wall, and blanket (0.7 in inboard and 0.9 in outboard thickness) and acting as a passive stabilizer. A reactive power of {approximately}2 MV A would be required for active feedback coils located outside of the TF coils {approximately}3 m to correct a 50-mm vertical displacement of the magnetic axis. A multipolar expansion technique used in the TSC analysis is also used to examine options that minimize stored energy. 10 refs., 8 figs., 2 tabs.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5393957
• Report Number(s): LA-UR-89-3327; CONF-891007-65; ON: DE90002441; TRN: 89-029809
• Resource Relation: Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TOKAMAK DEVICES
PLASMA INSTABILITY
DESIGN
FEEDBACK
FIRST WALL
PLASMA SCRAPE-OFF LAYER
PRESSURE VESSELS
BOUNDARY LAYERS
CLOSED PLASMA DEVICES
CONTAINERS
INSTABILITY
LAYERS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
700107* - Fusion Energy- Plasma Research- Instabilities