Community Research and Development Information Service - CORDIS

Abstract

In ITER, the ion cyclotron heating (ICH) system should routinely and reliably operate at a power level close to the installed power (20 MW) in quasi-continuous operation. The operation will be efficient and reliable only if plasma coupling and absorption of the fast wave on the plasma bulk are optimized, parasitic power losses in the plasma edge minimized, and the RF power flow, from the wave launching structure to the absorption layer, efficiently maintained against the effects of significant load variations. In this paper the ion cyclotron launcher proposed in the ITER Final Design Report (FDR) is briefly reviewed and a number of design changes are proposed, without any modification of the basic layout, in order to simplify construction and maintenance and to improve the performance and reliability of operation.

Additional information

Authors: BOSIA G, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);BEAUMONT B, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);BREMOND S, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);VULLIEZ K, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An article published in: Nuclear Fusion 46 (2006), pp. S540-S549
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/10.1088/0029-5515/46/7/S13
Record Number: 200719119 / Last updated on: 2007-04-11
Category: PUBLICATION
Original language: en
Available languages: en