The ITER Magnet System

Mitchell, N.; Bessette, D.; Gallix, R.; Jong, C.; Knaster, J.; Libeyre, P.; Sborchia, C.; Simon, Fabrice

doi:10.1109/tasc.2008.921232

Cited by 261 publications

(103 citation statements)

References 6 publications

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“…This will be done primarily to evaluate the test facilities' preparation technique for internal tin (prevention of Sn leakage), and will also test in a range more realistic for internal tin. The second effort will involve NbTi strand, which is used in the ITER Poloidal Field (PF) conductor [6]. This benchmarking is anticipated to cover the same scope as the current effort, although as there is no reaction heat treatment needed for NbTi, an "IO-prepared" round of testing is not envisioned.…”

Section: Discussion and Future Workmentioning

confidence: 99%

World-Wide Benchmarking of ITER ${\rm Nb}_{3}{\rm Sn}$ Strand Test Facilities

Jewell

Boutboul²,

Oberli³

et al. 2010

IEEE Trans. Appl. Supercond.

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Abstract-The world-wide procurement of Nb 3 Sn and NbTi for the ITER superconducting magnet systems will involve eight to ten strand suppliers from six Domestic Agencies (DAs) on three continents. To ensure accurate and consistent measurement of the physical and superconducting properties of the composite strand, a strand test facility benchmarking effort was initiated in August 2008. The objectives of this effort are to assess and improve the superconducting strand test and sample preparation technologies at each DA and supplier, in preparation for the more than ten thousand samples that will be tested during ITER procurement.The present benchmarking includes tests for critical current ( c ),-index, hysteresis loss ( hys ), residual resistivity ratio ( ), Future benchmarking efforts will include an annual cross-check of supplier and DA facilities, and also a round of internal tin Nb 3 Sn samples to assess each contributor's sample-preparation techniques. A separate round of NbTi benchmarking is also envisioned.

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Section: Discussion and Future Workmentioning

confidence: 99%

World-Wide Benchmarking of ITER ${\rm Nb}_{3}{\rm Sn}$ Strand Test Facilities

Jewell

Boutboul²,

Oberli³

et al. 2010

IEEE Trans. Appl. Supercond.

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“…The magnet system [4] is made up of 18 Toroidal Field (TF) coils, a 6-module Central Solenoid (CS), 6 Poloidal Field (PF) coils, 9 pairs of Correction Coils (CC) and High Temperature Superconducting Current Leads made of Ag-Au BiSCCO 2223. The TF coils field confines the charged particles in the plasma.…”

Section: Main Componentsmentioning

confidence: 99%

Challenges for Cryogenics at Iter

Serio¹,

Weisend²

2010

AIP Conference Proceedings

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Nuclear fusion of light nuclei is a promising option to provide clean, safe and cost competitive energy in the future. The ITER experimental reactor being designed by seven partners representing more than half of the world population will be assembled at Cadarache, South of France in the next decade. It is a thermonuclear fusion Tokamak that requires high magnetic fields to confine and stabilize the plasma. Cryogenic technology is extensively employed to achieve low-temperature conditions for the magnet and vacuum pumping systems. Efficient and reliable continuous operation shall be achieved despite unprecedented dynamic heat loads due to magnetic field variations and neutron production from the fusion reaction. Constraints and requirements of the largest superconducting Tokamak machine have been analyzed. Safety and technical risks have been initially assessed and proposals to mitigate the consequences analyzed. Industrial standards and components are being investigated to anticipate the requirements of reliable and efficient large scale energy production. After describing the basic features of ITER and its cryogenic system, we shall present the key design requirements, improvements, optimizations and challenges.

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“…A high and steady magnetic field needs to be produced to confine the deuterium (D)-tritium (T) burning plasma inside the ITER Tokamak nuclear fusion reactor. According to the previous ITER plan, hundreds of tons of superconducting cables made from NbTi and Nb 3 Sn strands have been fabricated to assemble 18 Nb 3 Sn toroidal field (TF) coils, a 6-module Nb 3 Sn central solenoid (CS) coil, six Nb-Ti poloidal field (PF) coils, and nine pairs of Nb-Ti correction coils (CC) [1][2][3]. ITER is aimed at demonstrating the feasibility of fusion energy, but for the next step, the development of a commercial fusion reactior there is a concern that, after irradiation, 93 Nb be transformed into the long-lived nuclide 94 Nb with a half-life of about 20,000 years [4,5].…”

Section: Introductionmentioning

confidence: 99%

Doping-Induced Isotopic Mg11B2 Bulk Superconductor for Fusion Application

et al. 2017

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Superconducting wires are widely used for fabricating magnetic coils in fusion reactors. Superconducting magnet system represents a key determinant of the thermal efficiency and the construction/operating costs of such a reactor. In consideration of the stability of 11 B against fast neutron irradiation and its lower induced radioactivation properties, MgB 2 superconductor with 11 B serving as the boron source is an alternative candidate for use in fusion reactors with a severe high neutron flux environment. In the present work, the glycine-doped Mg 11 B 2 bulk superconductor was synthesized from isotopic 11 B powder to enhance the high field properties. The critical current density was enhanced (10 3 A·cm −2 at 20 K and 5 T) over the entire field in contrast with the sample prepared from natural boron.

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The ITER Magnet System

Cited by 261 publications

References 6 publications

World-Wide Benchmarking of ITER ${\rm Nb}_{3}{\rm Sn}$ Strand Test Facilities

World-Wide Benchmarking of ITER ${\rm Nb}_{3}{\rm Sn}$ Strand Test Facilities

Challenges for Cryogenics at Iter

Doping-Induced Isotopic Mg11B2 Bulk Superconductor for Fusion Application

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