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Tronza V.I.,Center Domestic Agency DA | Lelekhov S.A.,Center Domestic Agency DA | Patrikeev V.M.,RAS Research Center Kurchatov Institute | Svertnev S.A.,RAS Research Center Kurchatov Institute | And 3 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2015

Conductors for winding ITER toroidal field magnets are cable-in-conduit type where multi-stage petals are twisted around central cooling spiral inserted into stainless steel jacket. Every conductor unit length and its components pass various tests during manufacturing and the final acceptance test consists of 760 m or 415 m long conductor global leak test and an investigation of conductor hydrodynamic performances. The hydraulic resistance is one of the main TF CICC's parameter to provide sufficient cool down and stable work of the magnet system during operation. Starting from 2011, when the first copper Dummy conductor was completed, 22 conductors in total were tested in a test facility that was designed and manufactured at National Research Centre 'Kurchatov Institute.' A scheme of the pressure drop test facility, measurements technique and results of mass flow rate measurements depending on inlet and outlet pressure difference are presented in this work. Measurements were carried out by flowing nitrogen gas through conductor at room temperature. However, in accordance with the theory of turbulent self-similarity it is possible to develop a simple criterion for estimation of hydraulic resistance at any temperature. The model of two parallel independent flows has been used. The simple explanation of mass flow rate non-linearity at small pressure difference has been provided. © 2002-2011 IEEE.

Tronza V.I.,Center DA | Kravtsov D.E.,Center DA | Zernov S.M.,JSC TVEL | Shlyakhov M.Y.,JSC TVEL | And 12 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2016

The ITER toroidal field (TF) magnet system consists of 18 D-shaped coils, each of which is formed by five regular double pancakes (rDP) and two side double pancakes (sDP). Manufacturing of conductors for the TF coils, which are Nb 3Sn-based cable-in-conduit conductors, has been shared among six ITER Domestic Agencies, including the Russian Federation (RF). The RF share includes manufacturing of eighteen 760-m conductors for rDP and eight 415-m conductors for sDP, i.e., almost 4 out of 18 TF coils will be produced from the conductors supplied by RF. In order to fulfil project obligations, facilities for Nb 3Sn strand, cable, and conductor production had been established, and after successful qualifications, the manufacturing phase began. The manufacturing activities went on for six years, starting with the first strand production in 2009 and finishing with a successful wrap-up of conductor manufacturing and delivery in 2015. In this paper, highlights of the TF conductor production from the superconducting strand manufacturing up to the results of conductor full-size sample tests in the SULTAN facility are presented. © 2016 IEEE.

Krasilnikov A.V.,Institution Project Center | Abdyuhanov I.M.,JSC VNIINM | Aleksandrov E.V.,Institution Project Center | Alekseev A.G.,RAS Research Center Kurchatov Institute | And 39 more authors.
Nuclear Fusion | Year: 2015

Due to the development of the ITER project, the requirements of the technical parameters of the ITER systems were more precisely and practically determined to be at higher levels. The essential increase of the ITER system characteristics happened recently. A number of prototypes were manufactured and tests were carried out. The results of the development and manufacture of 25 ITER systems, subject to the Russian Federation's obligations in the ITER project, are described. © 2015 IAEA, Vienna.

Tronza V.I.,Center Domestic Agency | Pantsyrny V.I.,Center Domestic Agency | Stepanov B.,Ecole Polytechnique Federale de Lausanne | Bruzzone P.,Ecole Polytechnique Federale de Lausanne | And 8 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2013

A conductor for ITER toroidal field (TF) coils is the cable-in-conduit conductor (CICC) type, which is made of Nb3Sn superconducting strands encased in a stainless steel tubular jacket. A 120-m-long prototype has been designed in accordance with ITER requirements and manufactured prior to production of 26 full-sized CICC lengths that are the contribution of Russia to the ITER TF magnet system. Ten meters of the prototype have been used to produce a sample for testing in the SULTAN facility in order to qualify the strand/cable/jacket combination. A test aimed at qualifying the conductor performance based on Tcs measurements in representative condition regarding the transport current and magnetic field has been carried out. At the same time, the test was used to compare the conductor behavior after different heat treatment cycles. Each of two legs has been reacted in accordance with one of the specified heat treatment cycles for the ITER TF conductor. Test results are presented and discussed. Based on the test results, the eligibility of the conductor for the ITER TF magnet system has been assessed. © 2002-2011 IEEE.

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