The effects of field reversal on the Alcator C-Mod divertor
Creators
- 1. Massachusetts Inst. of Tech., Cambridge, MA (United States). Plasma Fusion Center
Description
Imbalances between the inboard and outboard legs of the single null divertor in tokamak Alcator C-Mod are observed to reverse when the direction of the toroidal field is reversed. These imbalances are measured by embedded probes in the target plates, tomographic reconstructions of bolometry and line radiation, and visible imaging. Density imbalances of about a factor of ten at the targets are observed at moderate density, decreasing as the density is raised until they are almost balanced. The data indicate that the electron pressure is not imbalanced, thus arguing against momentum imbalance as the cause of these drift-induced effects. Instead, power flux imbalance caused by Er ''and'' B convection, and enhanced by radiation, is suggested as the underlying cause. (Author)
Additional details
Publishing Information
- Journal Title
- Plasma Physics and Controlled Fusion
- Journal Volume
- 37
- Journal Issue
- 12
- Journal Page Range
- p. 1389-1406.
- ISSN
- 0741-3335
- CODEN
- PPCFET
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 27024602
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ALCATOR DEVICE; DIVERTORS; ENERGY BALANCE; H-MODE PLASMA CONFINEMENT; HEAT FLUX; MAGNETIC FIELD REVERSAL; RADIANT HEAT TRANSFER; TOROIDAL CONFIGURATION
- Descriptors DEC
- ANNULAR SPACE; CLOSED CONFIGURATIONS; CLOSED PLASMA DEVICES; CONFIGURATION; CONFINEMENT; ENERGY TRANSFER; HEAT TRANSFER; MAGNETIC FIELD CONFIGURATIONS; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES