JET status and prospects

fYear

1991

fDate

30 Sep-3 Oct 1991

Firstpage

162

Abstract

A description of the technical status of the JET (Joint European Torus) machine and essential systems is given first. A feature of 1991 operation is the presence in the JET vessel of both graphite and beryllium X-point dump plates, in order to carry out a comparative assessment of these two materials. The 1991 experimental program has been successful and has included the study of a number of operation modes relevant to the next generation of machines. However, performance is still limited by impurity influxes. The pumped divertor experiment planned to start in 1993 aims at testing impurity control techniques in conditions relevant for the next step. In preparation for the deuterium-tritium phase of operation, an experiment using a small quantity of tritium in JET is planned. This experiment is expected to yield essential information on physics, technological, and safety aspects of tritium operation

Keywords

Tokamak devices; fusion reactor materials; fusion reactor theory and design; plasma toroidal confinement; Be; C; JET; Joint European Torus; T₂; X-point dump plates; impurity control techniques; impurity influxes; pumped divertor experiment; Fuels; Heating; Impurities; Physics; Plasma density; Plasma properties; Plasma temperature; Pumps; Temperature distribution; Testing;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

0-7803-0132-3

Type

conf

DOI

10.1109/FUSION.1991.218926

Filename

218926