Optimization of the ITER electron cyclotron equatorial launcher for improved heating and current drive functional capabilities
Creators
- 1. Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche, EURATOM-ENEA-CNR Association, via Cozzi 53, 20125 Milano (Italy)
- 2. ITER Organization, 13108 Saint-Paul-lez-Durance (France)
- 3. Fusion for Energy, c/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona (Spain)
Description
The design of the ITER Electron Cyclotron Heating and Current Drive (EC H and CD) system has evolved in the last years both in goals and functionalities by considering an expanded range of applications. A large effort has been devoted to a better integration of the equatorial and the upper launchers, both from the point of view of the performance and of the design impact on the engineering constraints. However, from the analysis of the ECCD performance in two references H-mode scenarios at burn (the inductive H-mode and the advanced non-inductive scenario), it was clear that the EC power deposition was not optimal for steady-state applications in the plasma region around mid radius. An optimization study of the equatorial launcher is presented here aiming at removing this limitation of the EC system capabilities. Changing the steering of the equatorial launcher from toroidal to poloidal ensures EC power deposition out to the normalized toroidal radius ρ ≈ 0.6, and nearly doubles the EC driven current around mid radius, without significant performance degradation in the core plasma region. In addition to the improved performance, the proposed design change is able to relax some engineering design constraints on both launchers
Additional details
Identifiers
- DOI
- 10.1063/1.4884352;
Publishing Information
- Journal Title
- Physics of Plasmas
- Journal Volume
- 21
- Journal Issue
- 6
- Journal Page Range
- p. 061504-061504.7
- ISSN
- 1070-664X
- CODEN
- PHPAEN
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46006120
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CYCLOTRONS; DESIGN; ECR CURRENT DRIVE; ECR HEATING; ELECTRONS; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; LIMITING VALUES; OPTIMIZATION; PERFORMANCE; PLASMA; STEADY-STATE CONDITIONS
- Descriptors DEC
- ACCELERATORS; CLOSED PLASMA DEVICES; CONFINEMENT; CYCLIC ACCELERATORS; ELEMENTARY PARTICLES; FERMIONS; HEATING; HIGH-FREQUENCY HEATING; LEPTONS; MAGNETIC CONFINEMENT; NON-INDUCTIVE CURRENT DRIVE; PLASMA CONFINEMENT; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- (c) 2014 EURATOM