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
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