Published March 2012 | Version v1
Journal article

Lithization of the FTU tokamak with a critical amount of lithium injection

  • 1. Associazione EURATOM-ENEA sulla Fusione, Centro Ricerche di Frascati, C.P. 65 00044 Frascati, Rome (Italy)
  • 2. TRINITI, Troitsk, Moscow reg. 142190 (Russian Federation)
  • 3. Institute of Plasma Physics and Laser Microfusion, EURATOM Association, 01-497, Warsaw (Poland)

Description

FTU plasma discharges with an extremely high amount of Li injection have been performed using a poloidal liquid lithium limiter acting as the principal Li source in the shadow of the main TZN toroidal limiter. Very peculiar of these discharges is the formation of a 'virtual' toroidal lithium limiter that redistributes the energy flux to the tokamak vessel first wall by radiative processes and therefore decreases the heat load onto the Mo limiter. These experiments contribute to the investigation of a more complex scenario that will possibly be faced by a project of a liquid lithium divertor in a tokamak with high additional power (or high power load on to the targets). (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/0741-3335/54/3/035001

Additional details

Publishing Information

Journal Title
Plasma Physics and Controlled Fusion
Journal Volume
54
Journal Issue
3
Journal Page Range
[10 p.]
ISSN
0741-3335
CODEN
PPCFET

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43128376
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DIVERTORS; ELECTRIC DISCHARGES; FIRST WALL; FT TOKAMAK; HEATING LOAD; LIMITERS; LITHIUM; PLASMA; PLASMA PRODUCTION
Descriptors DEC
ALKALI METALS; CLOSED PLASMA DEVICES; ELEMENTS; METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES