Progress in the ITER electron cyclotron heating and current drive system design

被引：10

作者：

Omori, Toshimichi ^{[1
]}

Albajar, Ferran ^{[2
]}

Bonicelli, Tullio ^{[2
]}

Carannante, Giuseppe ^{[2
]}

Cavinato, Mario ^{[2
]}

Cismondi, Fabio ^{[2
]}

Darbos, Caroline ^{[1
]}

Denisov, Grigory ^{[3
]}

Farina, Daniela ^{[4
]}

Gagliardi, Mario ^{[2
]}

Gandini, Franco ^{[1
]}

Gassmann, Thibault ^{[1
]}

Goodman, Timothy ^{[5
]}

Hanson, Gregory ^{[6
]}

Henderson, Mark A. ^{[1
]}

Kajiwara, Ken ^{[7
]}

McElhaney, Karen ^{[6
]}

Nousiainen, Risto ^{[2
]}

Oda, Yasuhisa ^{[7
]}

Oustinov, Alexander ^{[3
]}

Parmar, Darshankumar ^{[8
]}

Popov, Vladimir L. ^{[3
]}

Purohit, Dharmesh ^{[1
]}

Rao, Shambhu Laxmikanth ^{[8
]}

Rasmussen, David ^{[6
]}

Rathod, Vipal ^{[8
]}

Ronden, Dennis M. S. ^{[9
]}

Saibene, Gabriella ^{[2
]}

Sakamoto, Keishi ^{[7
]}

Sartori, Filippo ^{[2
]}

Scherer, Theo ^{[10
]}

Singhh, Narinder Pal ^{[8
]}

Strauss, Dirk ^{[10
]}

Takahashi, Koji ^{[7
]}

机构：

[1] ITER Org, F-13067 St Paul Les Durance, France

[2] Fus Energy, Barcelona 08019, Spain

[3] Russian Acad Sci, Inst Appl Phys, Nizhnii Novgorod 603950, Russia

[4] Assoc EURATOM ENEA CNR, Ist Fis Plasma, Milan, Italy

[5] EPFL Ecublens, Assoc EURATOM Confederat Suisse, CRPP, CH-1015 Lausanne, Switzerland

[6] ORNL, US ITER Project Off, Oak Ridge, TN 37831 USA

[7] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

[8] Inst Plasma Res, Bhat 382428, Gandhinagar, India

[9] FOM Inst DIFFER, NL-3430 BE Nieuwegein, Netherlands

[10] Assoc EURATOM KIT, IMF, KIT, D-76021 Karlsruhe, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2015年 / 96-97卷

关键词：

ITER; Electron cyclotron; Heating; Current drive;

D O I：

10.1016/j.fusengdes.2014.12.023

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

An electron cyclotron system is one of the four auxiliary plasma heating systems to be installed on the ITER tokamak. The ITER EC system consists of 24 gyrotrons with associated 12 high voltage power supplies, a set of evacuated transmission lines and two types of launchers. The whole system is designed to inject 20 MW of microwave power at 170 GHz into the plasma. The primary functions of the system include plasma start-up, central heating and current drive, and magneto-hydrodynamic instabilities control. The design takes present day technology and extends towards high power CW operation, which represents a large step forward as compared to the present state of the art. The ITER EC system will be a stepping stone to future EC systems for DEMO and beyond. The EC system is faced with significant challenges, which not only includes an advanced microwave system for plasma heating and current drive applications but also has to comply with stringent requirements associated with nuclear safety as ITER became the first fusion device licensed as basic nuclear installations as of 9 November 2012. Since conceptual design of the EC system established in 2007, the EC system has progressed to a preliminary design stage in 2012, and is now moving forward towards a final design. The majority of the subsystems have completed the detailed design and now advancing towards the final design completion. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：547 / 552

页数：6

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