Vertical stability, high elongation, and the consequences of loss of vertical control on DIII-D

Conference · Sat Sep 01 00:00:00 EDT 1990

OSTI ID:6446263

Kellman, A G; Ferron, J R; Jensen, T H; Lao, L L; Luxon, J L; Skinner, D G; Strait, E J; Reis, E; Taylor, T S; Turnbull, A D ^[1]; Lazarus, E A ^[2]; Lister, J B ^[3]

---

1. General Atomics, San Diego, CA (USA)
2. Oak Ridge National Lab., TN (USA)
3. Centre de Recherches en Physique des Plasmas, Lausanne (Switzerland)

Recent modifications to the vertical control system for DIII-D has enabled operation of discharges with vertical elongation {kappa}, up to 2.5. When vertical stability is lost, a disruption follows and a large vertical force on the vacuum vessel is observed. The loss of plasma energy begins when the edge safety factor q is 2 but the current decay does not begin until q {approximately}1.3. Current flow on the open field lines in the plasma scrapeoff layer has been measured and the magnitude and distribution of these currents can explain the observed force on the vessel. Equilibrium calculations and simulation of this vertical displacement episode are presented. 7 refs., 4 figs.

• Research Organization: General Atomics, San Diego, CA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC03-89ER51114
• OSTI ID: 6446263
• Report Number(s): GA-A-20238; CONF-900918-10; ON: DE91001324; TRN: 90-032672
• Resource Relation: Conference: 16. symposium on fusion technology, London (UK), 3-7 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DOUBLET REACTORS
CONTROL SYSTEMS
CONFINEMENT TIME
ELONGATION
MODIFICATIONS
PLASMA DISRUPTION
PLASMA SCRAPE-OFF LAYER
STABILITY
BOUNDARY LAYERS
LAYERS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700101 - Fusion Energy- Plasma Research- Confinement
Heating
& Production