Biasing and improved divertor performance on the TdeV tokamak
Description
Electrical biasing of the plasma is used on the TdeV tokamak (R = 0.86 m, a = 0.26 m, Ip = 250 kA) to improve the divertor impurity confinement and exhaust pumping capability, two important issues for fusion research. Plasma biasing, applied through the divertor neutralization plates, strongly affects the plasma properties in the scrape off layer (SOL), modifying the plasma potential, the edge density profile and ion flow in the SOL. The ErxB flow, associated with the radial electric field established near the separatrix, increases impurity transport into the divertor. Biasing greatly increases the efficiency of the divertor. There is a linear dependence of divertor pressure on the bias voltage; negative biasing having the strongest dependence. For negative biasing, divertor pressure is a non linear function of plasma density. Negative biasing also increases impurity retention in the divertor. The high pressure and increased impurity retention in the divertor produced by negative plasma biasing can greatly increase the efficiency of a pumped divertor for plasma impurity control and He ash removal in a reactor. External fueling will compensate for the plasma transport to the divertor to maintain a constant plasma density
Additional details
Publishing Information
- Publisher
- IEEE Service Center.
- Imprint Place
- Piscataway, NJ (United States)
- ISBN
- 0-7803-1360-7
- Imprint Title
- IEEE International conference on plasma science. Conference record - Abstracts
- Imprint Pagination
- 250 p.
- Journal Page Range
- p. 118.
- ISSN
- 0730-9244
Conference
- Title
- 20. IEEE international conference on plasma sciences.
- Dates
- 7-9 Jun 1993.
- Place
- Vancouver (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25016678
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIVERTORS; ELECTRIC CONDUCTIVITY; HELIUM ASH; MAGNETIC SURFACES; PERFORMANCE; PLASMA IMPURITIES; PLASMA SCRAPE-OFF LAYER; REMOVAL; TOKAMAK DEVICES
- Descriptors DEC
- BOUNDARY LAYERS; CHARGED PARTICLES; CLOSED PLASMA DEVICES; ELECTRICAL PROPERTIES; HELIUM IONS; IMPURITIES; IONS; LAYERS; MAGNETIC FIELD CONFIGURATIONS; PHYSICAL PROPERTIES; THERMONUCLEAR DEVICES
Optional Information
- Secondary number(s)
- CONF-930652--.