THE JOINT EUROPEAN TORUS - INSTALLATION, 1ST RESULTS AND PROSPECTS

The paper provides a brief introduction to the main aims, overall design philosophy and the planned parameter range of the large tokamak device (major radius R equals 2. 96 m; horizontal and vertical minor radii, respectively: a equals 1. 25 m, b equals 2. 10 m; plasma current, I//p equals 4. 8 MA), the Joint European Torus (JET), situated on the Culham Laboratory site, UK, whose main objective is to obtain and study plasmas in conditions and with dimensions approaching those needed in a fusion reactor. The main emphasis is on initial operation in the Ohmic-heating phase, in which results are presented covering a wide range of parameters. The paper concludes with a description of planned future experiments on impurity control, additional heating, (ICRF approximately equals 15 MW, and neutral injection approximately equals 10 MW), and preparations for tritium operation.