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Udintsev V.S.,ITER Organization | Maquet P.,ITER Organization | Alexandrov E.,Russian Federation Domestic Agency | Casal N.,ITER Organization | And 24 more authors.
Fusion Engineering and Design | Year: 2015

The Diagnostic Generic Equatorial Port Plug (GEPP) is designed to be common to all equatorial port-based diagnostic systems. It is designed to survive throughout the lifetime of ITER for 20 years, 30,000 discharges, and 3000 disruptions. The EPP structure dimensions (without Diagnostic First Walls and Diagnostic Shield Modules) are L2.9 × W1.9 × H2.4 m3. The length of the fully integrated EPP is 3174 mm. The weight of the EPP structure is about 15 t, whereas the total weight of the integrated EPP may be up to 45 t. The EPP structure provides a flexible platform for a variety of diagnostics. The Diagnostic Shield Module assemblies, or drawers, allow a modular approach with respect to diagnostic integration and maintenance. In the nuclear phase of ITER operations, they will be remotely inserted into the EPP structure in the Hot Cell Facility. The port plug structure must also contribute to the nuclear shielding, or plugging, of the port and further contain circulated water to allow cooling during operation and heating during bake-out. The Final Design of the GEPP has been successfully passed in late 2013 and is now heading toward manufacturing. The final design of the GEPP includes interfaces, manufacturing, R&D, operation and maintenance, load cases and analysis of failure modes. © 2015 Elsevier B.V. Source

Belyakov V.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Bursikov A.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Klimchenko Y.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | Marushin E.,D.V. Efremov Scientific Research Institute of Eelectrophysical Apparatus | And 6 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2016

This paper describes the experience in PF1 dummy double pancake winding, which was performed in the Russian Federation in 2014-2015. The pancake was wound by the method of 'two-in-hand' stress-free winding with continuous chemical cleaning and sandblasting of the conductor surface followed by application of multilayered turn insulation. The winding was accomplished by a mobile flexibly scalable complex of equipment installed within the shortest possible time in a special 'clean room.' This complex has a number of advantages, such as mobility, cost effectiveness, independence, minimum attending personnel, synchronization of all operations under a unified automatic control system, continuous control, and possible fast correction of output parameters. © 2002-2011 IEEE. Source

Udintsev V.S.,ITER Organization | Portales M.,ITER Organization | Giacomin T.,ITER Organization | Darcourt O.,ITER Organization | And 16 more authors.
Fusion Engineering and Design | Year: 2013

Development of the diagnostics for ITER tokamak, which is presently under construction by several international partners at Cadarache in France, is a major challenge because of severe environment, strict engineering requirements, and the need for high reliability in the measurements. The diagnostic systems in the upper, equatorial and lower port cells on ITER are designed to be integrated within the interspace and port cell support structures. These structures are interfacing with remote handling rail system for the cask operations, thus facilitating the removal and installation of the diagnostics in the port and hence minimizing time for working close to the tokamak. In this paper, the challenges associated with the integration of the diagnostics in the port interspace and port cell, as well as their solutions will be addressed and presented. The interspace and the port cell support structures, as well as their interfaces with the biological shield, will be discussed. © 2013 Elsevier B.V. All rights reserved. Source

Udintsev V.S.,ITER Organization | Vayakis G.,ITER Organization | Bora D.,ITER Organization | Direz M.-F.,ITER Organization | And 18 more authors.
EPJ Web of Conferences | Year: 2012

The Electron Cyclotron Emission (ECE) diagnostic provides essential information for plasma operation and for establishing performance characteristics in ITER. Recently, the design of the ITER ECE diagnostic has been taken through the conceptual design review and now entering the detailed design phase [1, 2]. The baseline ECE system on ITER permits measurements of both the X- and O-mode radiation in the frequency range from 70 GHz up to 1 THz along two lines-of-sight, perpendicular and oblique at about 10 degrees, in the equatorial port. The system as planned meets the ITER measurement requirements. Nevertheless, there are several other mm-wave diagnostics in ITER, such as HFS, LFS and plasma position reflectometry, as well as Collective Thomson scattering system, whose transmission lines allow, in principle, additional measurements of parts of the ECE spectrum with upgrades of their back-ends, improvements in filtering and/or additional receivers. A discussion of whether and how supposedly to enable such ECE measurements is given here. © Owned by the authors, published by EDP Sciences, 2012. Source

Sadakov S.,ITER Organization | Khomiakov S.,Russian Federation Domestic Agency | Calcagno B.,ITER Organization | Chappuis Ph.,ITER Organization | And 8 more authors.
Fusion Engineering and Design | Year: 2013

Main function of the ITER blanket system [1-3] is to shield the vacuum vessel (VV) from nuclear radiation and thermal energy coming from the plasma. Blanket system consists of discrete blanket modules (BM). Each BM is composed of a first wall panel and a shield block (SB). The shield block is attached to the VV by means of four flexible supports and three or four shear keys, through key pads. All listed supports do have parts with ceramic electro-insulating coatings necessary to exclude the largest loops of eddy currents and restrict EM loads. Electrical connection of each SB to the VV is through two elastic electrical straps. Cooling water is supplied to each BM by one coaxial water connector. This paper summarizes the recent evolution of the blanket attachment system toward design solutions compatible with design loads and numbers of load cycles, and providing sufficient reliability and durability. This evolution was done in a frame of pre-defined external interfaces. The ongoing supporting R&D is also briefly described. © 2013 Elsevier B.V. Source

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