Progress of the ECRH Upper Launcher design for ITER

The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma heating and MHD stabilization. The system consists of an array of 24 gyrotrons with power supplies coupled to a set of transmission lines guiding the beams to the four upper and the equatorial launcher. The front steering upper launcher design described herein has passed successfully the preliminary design review, and it is presently in the final design stage. The launcher consists of a millimeter wave system and steering mechanism with neutron shielding integrated into an upper port plug with the plasma facing blanket shield module (in-vessel) and a set of ex-vessel waveguides connecting the launcher to the transmission lines. Part of the transmission lines are the ultra-low loss CVD torus diamond windows and a shutter valve, a miter bend section and the feedthroughs integrated in the plug closure plate. These components are connected by corrugated waveguides and form together the first confinement system (FCS). In-vessel, the millimeter-wave system includes a quasi-optical beam propagation system including four mirror sets and a front steering mirror. The millimeter wave system is integrated into a specifically optimized upper port plug providing structural stability to withstand plasma disruption force and the high heat load from the plasma side with a dedicated blanket shield module. A recent update in the ITER interface definition has resulted in the recession of the upper port plug first wall panels, which is now integrated into the design. Apart from the millimeter wave system the upper port plug houses also a set of shield blocks which provide neutron shielding. An overview of the actual ITER ECRH Upper Launcher is given together with some highlights of the design. (C) 2014 Elsevier B.V. All rights reserved.

[1]  Koji Takahashi,et al.  Progress of ITER equatorial electron cyclotron launcher design for physics optimization and toward final design , 2011 .

[2]  Dennis Ronden,et al.  The ITER EC H&CD Upper Launcher: Maintenance concepts , 2013 .

[3]  Theo Scherer,et al.  The ITER EC H&CD upper launcher: EM disruption analyses , 2013 .

[4]  B. Weinhorst,et al.  The ITER ECH & CD Upper Launcher: Steps towards final design of the first confinement system , 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).

[5]  Dennis Ronden,et al.  Analysis of ITER upper port plug remote handling maintenance scenarios , 2012 .

[6]  M. A. Shapiro,et al.  The EC H&CD Transmission Line for ITER , 2011 .

[7]  Theo Scherer,et al.  The ITER EC H&CD Upper Launcher: Seismic analysis , 2014 .

[8]  G. Gantenbein,et al.  Preliminary design of the ITER ECH upper launcher , 2011, 2011 Abstracts IEEE International Conference on Plasma Science.

[9]  Arkady Serikov,et al.  Status of the neutronic analyses for the electron cyclotron-heating upper launcher of ITER , 2013 .

[10]  Olivier Sauter,et al.  On the requirements to control neoclassical tearing modes in burning plasmas , 2010 .

[11]  A. Meier,et al.  Experimental analysis of the inserted waveguide CVD diamond window prototype for the ITER ECRH upper launcher , 2011, 2011 International Conference on Infrared, Millimeter, and Terahertz Waves.

[12]  B. Weinhorst,et al.  The ITER EC-H&CD Upper Launcher: FEM analyses of the blanket shield module with respect to surface and nuclear heat loads , 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).

[13]  Timothy Goodman,et al.  Overview of the ITER EC H&CD system and its capabilities , 2011 .

[14]  A. Meier,et al.  Investigations of dielectric RF properties of ultra low loss CVD diamond disks for fusion applications , 2009, International Conference on Infrared, Millimeter, and Terahertz Waves.