ITER current drive and heating system
Description
Resulting from the Conceptual Design Activities (1988-1990) by the parties involved in the International Thermonuclear Experimental Reactor (ITER) project, this document summarizes the design requirements and the Conceptual Design Descriptions for each of the principal subsystems and design options of the ITER Current Drive and Heating System. The ITER Current Drive and Heating System has to (i) ensure a reliable breakdown during the formation phase, (ii) contribute to the current ramp-up, (iii) heat the plasma to ignition, (iv) maintain a quasi-steady burn with an amplification factor Q of five or more, (v) enable global and local current profile and burn control, and (vi) to assist in the plasma shut down. In order to meet all the requirements, two combinations of current drive and heating methods were chosen, the ''reference'' (a 75 MW, 1.3 MeV Neutral Beam system, a 50 MW, 5 GHz Lower Hybrid system, plus a 20 MW, 120 GHz Electron Cyclotron system) and the ''alternative'' (a 130 MW, 15-80 MHz Ion Cyclotron system, a 50 MW, 5 GHz Lower Hybrid system, plus a 20 MW, 120 GHz Electron Cyclotron system). Two supplementary systems (a 20 MW, 140-160 GHz Electron Cyclotron system and a 20 MW, 70-110 MHz Ion Cyclotron system) were specified. These supplementary systems could significantly improve the flexibility and the resources of the current drive and heating system. The design and its motivation for all its subsystems (Neutral Beam, Lower Hybrid, Electron Cyclotron, and Ion Cyclotron) are presented. Refs, figs and tabs
Availability note (English)
MF available from INIS under the Report Number.Additional details
Additional titles
- Augmented title (English)
- International Thermonuclear Experimental Reactor
Publishing Information
- Imprint Pagination
- 209 p.
- Journal Issue
- No. 32
- Series
- ITER documentation series.
- Report number
- INIS-mf--13101
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 23024412
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BEAM INJECTION HEATING; CURRENT-DRIVE HEATING; ECR HEATING; EXPERIMENT PLANNING; ICR HEATING; ITER TOKAMAK; LOWER HYBRID HEATING; NON-INDUCTIVE CURRENT DRIVE; PLASMA RADIAL PROFILES; SPECIFICATIONS; START-UP; THERMONUCLEAR IGNITION
- Descriptors DEC
- CLOSED PLASMA DEVICES; HEATING; HIGH-FREQUENCY HEATING; PLANNING; PLASMA HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES