skip to main content

SciTech ConnectSciTech Connect

Title: Optimization of the ITER electron cyclotron equatorial launcher for improved heating and current drive functional capabilities

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.
Authors:
;  [1] ;  [2] ;  [3]
  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)
Publication Date:
OSTI Identifier:
22299947
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Plasmas; Journal Volume: 21; Journal Issue: 6; Other Information: (c) 2014 EURATOM; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CYCLOTRONS; DESIGN; ECR CURRENT DRIVE; ECR HEATING; ELECTRONS; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; LIMITING VALUES; OPTIMIZATION; PERFORMANCE; PLASMA; STEADY-STATE CONDITIONS