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Plasma facing components like the ITER blanket shield modules (BSMs) often consist of a first wall and a shield block that are mounted to a vacuum vessel wall. The ITER mount is comprised of an Inconel bolt, Ni-Al-bronze collar, insulating layers of alumina and a flexible Inconel cartridge that allows compliance to reduce stress. Here we describe our efforts to perform multiphysics simulations on...
In the frame of the new grant signed in November 2011 between Fusion for Energy (F4E) and the ECHUL-CA consortium, the development process of the Electron Cyclotron Heating and Current Drive (EC H&CD) Upper Launcher (UL) in ITER has moved a step towards the final design phase. The Blanket Shield Module (BSM) is a plasma facing component located at the tip of the launcher. The structure consists...
To counteract plasma instabilities, Electron Cyclotron launchers with a total Millimeter-wave power of 20 MW are installed into four of the ITER Upper Ports. Each Mm-wave-system consists of eight transmission lines; a quasi-optical focusing mirror system and two steerable front mirrors to be capable of injecting the beams over the range plasma instabilities are susceptible to occur. The Mm-wave-systems...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of a large aperture diagnostic were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding...
Four of the 16 ITER upper port plugs will be devoted to electron cyclotron resonance heating (ECRH) in order to control the magneto-hydrodynamic (MHD) instabilities.In order to achieve the stabilisation of the neoclassical tearing modes (NTM) and sawtooth oscillation, a deposition of a very localized, narrow and peaked current density profile over a broad poloidal steering range at the ITER rational...
Four ECH Upper Port Plugs are foreseen at ITER for counteracting plasma instabilities based on the injection of up to 20 MW mm-wave power at 170 GHz into the plasma. The required targeting of flux surfaces will be achieved by angular steering in the poloidal direction. The paper describes the main components of the mm-wave and structural system for the current reference design of the extended physics...
The development work carried out in Europe on the design of standard blanket shield modules for ITER has been continued, with the objective of further decreasing the fabrication and maintenance costs and demonstrating viable solutions for the most complicated special shield module of the neutral beam injector (NBI) region.A modified attachment system of first wall panels (FWP) to the shield block,...
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