Published January 1990 | Version v1
Report

Impurity behaviour during ECH in the Texas experimental tokamak

  • 1. Texas Univ., Austin, TX (USA). Fusion Research Center
  • 2. Auburn Univ., AL (USA)

Description

During electron cyclotron heating in the Texas Experimental Tokamak, the concentration of metallic impurities near the plasma center increased. In the experiment, a 60 GHz predominantly 0-mode wave was launched from the low-field side of the tokamak plasma. Approximately 100 kW (equivalent to 1/3 of the OH power) was deposited within a few centimeters of the plasma major radius. From analysis of the impurity behavior, it appears that the ECH induced both a substantial increase in the edge impurity source and a modest reduction in the inward impurity transport. Specifically, the edge source was increased by as much as 40%, while for p>0.7, the impurity diffusion was increased by 50%. The enhanced impurity diffusion occurs simultaneously with a reduction in particle confinement and with an increase in plasma potential. (author). 3 refs, 4 figs

Part of:
Impurity control in toroidal devices

Additional details

Publishing Information

Imprint Title
Impurity control in toroidal devices
Imprint Pagination
173 p.
Journal Page Range
p. 95-100.
Report number
IAEA-TECDOC--536

Conference

Title
Technical committee on impurity control.
Dates
13-15 Feb 1989.
Place
Naka-Gun (Japan).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21025698
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHARGED-PARTICLE TRANSPORT; DIFFUSION; ECR HEATING; IMPURITIES; TEXT DEVICES
Descriptors DEC
CLOSED PLASMA DEVICES; HEATING; HIGH-FREQUENCY HEATING; PLASMA HEATING; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Contract/Grant/Project number
Grant DE-FG05-88ER53267; Grant DE-FG05-88ER53266