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International thermonuclear engineering reactor (ITER) physics specifications provide engineering design requirements. They are based on experimental results obtained on the present day tokamaks and their extrapolation by numerical codes to the ITER parameters. The present paper summarizes recent results obtained in the ITER voluntary physics research and development programme conducted by four ITER parties and presents projections for ITER plasma performance, operational scenarios and plasma control obtained by the joint central team and home teams. The goal for the ITER experimental programme is demonstration of controlled ignition and sustained burn in deuterium-tritium plasmas and development of long pulse/steady state operational scenarios for fusion power production and experimental demonstration of their feasibility. ITER as a first reactor-scale machine will encounter problems which are essential for a tokamak reactor. The most important plasma physics issues are: energy and particle confinement of the core plasma in the ignited regime, power handling and divertor operation consistent with ignited plasma, advancing in high beta regimes and plasma operation near or above the Greenwald density limit. It is also very important to develop reliable plasma control systems to avoid or mitigate plasma disruptions.

Additional information

Authors: PUTVINSKI S ET AL, ITER Joint Central Team, San Diego (US)
Bibliographic Reference: Article: Proceedings of the 16th IAEA Fusion Energy Conference (1996) pp. 464-465
Record Number: 199810142 / Last updated on: 1998-02-12
Original language: en
Available languages: en