Published July 1987 | Version v1
Journal article

Spectroscopic study of impurity behaviour in neutral beam heated and ohmically heated TFTR discharges

Description

Quantitative spectroscopic measurements of Zeff, impurity densities and radiated power losses have been made for ohmically heated and neutral beam heated TFTR discharges at a plasma current of 2.2 MA and a toroidal field of 4.7 T. Variations in these quantities with line average plasma density (n-bare) and beam power up to 5.6 MW are presented for discharges on a movable graphite limiter. A detailed discussion of the use of an impurity transport model to infer absolute impurity densities and radiative losses from line intensity and visible continuum measurements is given. These discharges were dominated by low-Z impurities, with carbon having a considerably higher density than oxygen, except in high n-bare Ohmic discharges where the densities of carbon and oxygen were comparable. Metallic impurity concentrations and radiative losses were small, resulting in hollow radiated power profiles and fractions of the input power radiated being 30-50% for Ohmic heating and 30% or less for beam heating. Spectroscopic estimates of the radiated power were in good agreement with bolometrically measured values. Because of an increase in the carbon density, Zeff rose from 2.0 to 2.8 as the beam power increased from 0 to 5.6 MW, pointing to a potentially serious dilution of the neutron producing plasma ions with increasing beam power. Both the low-Z and the metallic impurity concentrations were approximately constant with minor radius, indicating no central impurity accumulation in these discharges. (author)

Additional details

Publishing Information

Journal Title
Nucl. Fusion
Journal Volume
27
Journal Issue
7
Series
Nucl. Fusion.
Journal Page Range
1147-1164
ISSN
0029-5515
CODEN
NUFUA

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
18084028
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BEAM INJECTION HEATING; CHARGED-PARTICLE TRANSPORT; EXPERIMENTAL DATA; GRAPHITE; IMPURITIES; JOULE HEATING; LIMITERS; PLASMA DIAGNOSTICS; RADIATION FLUX; TFTR TOKAMAK
Descriptors DEC
CARBON; CLOSED PLASMA DEVICES; DATA; ELEMENTS; HEATING; INFORMATION; NONMETALS; NUMERICAL DATA; PLASMA HEATING; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
28 refs, 21 figs, 5 tabs.