Development and manufacturing of superconducting cable-in-conduit conductor for ITER

Sytnikov, V.E.; Peshkov, I. B.; Taran, Amir; Dolgosheev, P.I.; Ipatov, Yu. P.; Rychagov, A.; Svalov, G.G.; Mitrohin, V.

doi:10.1109/77.620823

Cited by 6 publications

(3 citation statements)

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“…One particularity of ITER conductor manufacture is that it requires dedicated 800-1000 m long jacketing lines where to store the welded jacket assemblies and to carry out cable insertion prior to compaction and spooling. The feasibility of the jacketing concept for long length CICCs was first demonstrated in the mid 1990's in RF [36]. Five out of the six DAs involved in ITER conductor production have decided to set up their own jacketing line (namely: CN, EU, JA, RF and US), while KO has decided to subcontract its jacketing work to the EU supplier.…”

Section: Iter Conductorsmentioning

confidence: 99%

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Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

174

118

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Taking the relay of the Large Hadron Collider (LHC) at CERN, ITER has become the largest project in applied superconductivity. In addition to its technical complexity, ITER is also a management challenge as it relies on an unprecedented collaboration of 7 partners, representing more than half of the world population, who provide 90% of the components as in-kind contributions. The ITER magnet system has a stored energy of 51 GJ and involves 6 of the ITER partners. The coils are wound from Cable-In-Conduit Conductors (CICCs) made up of superconducting and copper strands assembled into a fully transposed, rope-type cable, inserted into a conduit of butt-welded austenitic steel tubes. The conductors for the Toroidal Field (TF) and Central Solenoid (CS) coils require about 500 tons of Nb 3 Sn strands while the Poloidal Field (PF) and Correction Coil (CC) and busbar conductors need around 250 tons of Nb-Ti strands. The required amount of Nb 3 Sn strands far exceeds pre-existing industrial capacity and has called for a significant worldwide production scale up. The TF conductors are the first ITER components to be mass produced and are more than 50% complete. During its life time, the CS coil will have to sustain several tens of thousands of electromagnetic (EM) cycles to high current and field conditions, way beyond anything a large Nb 3 Sn coil has ever experienced. Following a comprehensive R&D program, a technical solution has been found for the CS conductor, which ensures stable performance versus EM and thermal cycling. Productions of PF, CC and busbar conductors are also underway. After an introduction to the ITER project and magnet system, we describe the ITER conductor procurements and the Quality Assurance/Quality Control programs that have been implemented to ensure production uniformity across numerous suppliers. Then, we provide examples of technical challenges that have been encountered and we present a status of ITER conductor production worldwide.

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Section: Iter Conductorsmentioning

confidence: 99%

“…One particularity of ITER conductor manufacture is that it requires dedicated 800-1000 m long jacketing lines to store the welded jacket assemblies and to carry out cable insertion prior to compaction and spooling. The feasibility of the jacketing concept for long length CICCs was first demonstrated in the mid 1990s in RF [39].…”

Section: Manufacturementioning

confidence: 99%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

174

118

View full text Add to dashboard Cite

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“…1). The TFCI conductor was manufactured in the Russian Federation [1], [2] and it was tested in the fall of 2001 in the bore of the Central Solenoid Model Coil (CSMC) in the JAERI facility at Naka, Japan [3]. The coil is cooled in parallel with the CSMC by forced-flow SHe at 4.5 K and 0.6 MPa, and was successfully operated up to the nominal current and field of 46 kA and 13 T.…”

Section: Introductionmentioning

confidence: 99%

Tests and analysis of quench propagation in the ITER toroidal field conductor insert

Savoldi

Portone²,

Zanino

2003

IEEE Trans. Appl. Supercond.

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The International Thermonuclear Experimental Reactor (ITER) Toroidal Field Conductor Insert (TFCI) has been tested at JAERI Naka, Japan, in 2001, in the background field of the Central Solenoid Model Coil. The TFCI, a well-instrumented 43 m long Nb 3 Sn solenoid with a thin Ti jacket, wound inside a SS mandrel and cooled by supercritical helium (SHe) at 4.5 K and 0.6 MPa, was successfully operated up to 46 kA and 13 T. Among others, tests of quench propagation, with delay time of the current dump up to 7 s, were performed driven by an inductive heater. The experimental results of these tests are presented. The hot spot temperature reached in the TFCI during the quench is qualitatively assessed. A more quantitative quench analysis is then performed using the Mithrandir code, confirming the qualitative estimation of the hot spot temperature and showing the importance of heat loss to the mandrel in the slowing down of quench propagation. The computed results well reproduce the main experimental features of the quench transient up to the current dump.

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