Reliability Considerations for the ITER Poloidal Field Coils

Simon, Fabrice; Ilyin, Y.; Lim, Byung Su; Cau, Francesca; Herzog, Robert; Stepanov, B.

doi:10.1109/tasc.2010.2040262

Cited by 12 publications

(6 citation statements)

References 5 publications

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“…The design of the PF conductors and their performance, especially for the high magnetic field coil PF6, has been demonstrated with the testing of the PF insert coil at Naka in 2008 [12]. The design of the coils was finalized in 2009 [13], but the design of some critical items, such as helium inlets, tails, joint and termination supports, is still ongoing. The PA for the manufacture of the five large PF coils to be fabricated by EU in a dedicated on-site facility was signed in 2009, while the one for the manufacture of PF1 in RF is under preparation and should be signed in early 2011.…”

Section: Pf Coilsmentioning

confidence: 99%

The ITER magnet systems: progress on construction

et al. 2013

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Construction of the ITER magnet systems has been started at the end of 2007 following the signature of the first procurement arrangements (PA) for the toroidal field (TF) conductors. Six ITER members are involved in the share of the ITER magnet components and, to date, eighteen PA between the ITER Organization and six domestic agencies have been signed. Substantial progress towards full-scale construction has been achieved with the placement of the first large manufacturing contracts, the production of several tens of tons of advanced Nb 3 Sn and NbTi strand, and the setup of large cabling and jacketing facilities. The detailed design of the coils and support structures has also been finalized. The qualification of the fabrication processes for the TF coils and poloidal field (PF) coils has been initiated. The detailed design of the central solenoid (CS) coils is being developed. The design of the correction coils (CCs) with their support structures has been finalized, as well as for the TF gravity supports and clamps of the PF coils. The manufacture of prototypes of the feeder lines and current leads has been started, while ITER is in charge of the procurement of the required magnet instrumentation. This paper provides a progress report on the ITER magnet construction as per December 2010.

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Section: Pf Coilsmentioning

confidence: 99%

The ITER magnet systems: progress on construction

et al. 2013

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“…Since the PF coil system provides magnetic fields for plasma shaping and position control with the Central Solenoid (CS) coil, it needs to be pulsed with fast variations of the coil current, leading to induced voltages of up to 14 kV on the coil terminals during operation [2]. The maximum current allowed in any PF coil is between 48 and 55 kA.…”

Section: Main Parameters and Tolerancesmentioning

confidence: 99%

“…All PF coils are designed to allow a DP to be bypassed with a superconducting jumper bus in the event of failure to avoid major disassembly of the tokamak in order to extract a PF coil and repair a failed DP. The loss of Ampere-turns in the repaired coil is recovered by increasing the operating current [2]. In 2008, the PF coils design and PF conductor layouts were changed to give a greater operational window for low-internal inductance plasmas during burn, to extend the operating window for plasmas with currents above 15 MA, and to improve the plasma vertical stability control [3].…”

Section: Introductionmentioning

confidence: 99%

Development of the ITER PF Coils

Lim

Simon

Ilin

et al. 2012

IEEE Trans. Appl. Supercond.

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The ITER Poloidal Field (PF) magnet system consists of six coils. Niobium-Titanium (NbTi) is used as superconducting material and cable-in-conduit conductor(CICC) type are used as a conductor. All coils are fabricated by stacking 6 to 9 double-pancakes wound by two-in-hand winding scheme. The six PF coils (PF1 to PF6) are attached to the Toroidal Field (TF) coil cases through flexible plates or sliding supports to allow small radial and vertical displacements. The outer diameters of the coils vary between 8 m and 24 m. Since the PF coil system provides magnetic field for plasma shaping and position control together with the Central Solenoid (CS) coil, it needs to operate in fast pulse mode, leading to induced voltages of up to 14 kV on the coil terminals during operation.PF coils will be procured by the European and Russian domestic agencies under separate procurement arrangements (PA). Manufacturing design, equipment installation including design and commissioning, and component qualification are the required first steps before entering series production. This paper presents the updated design for manufacturing of components such as tail, joint, clamp and protection cover. Their fabrication and assembly methods are also described. The paper concludes with a summary states report on component qualification program.

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“…One of the ITER design requirements is that the coils should be able to withstand the operating voltage between the terminals. Consequently, the design of the insulation, coil terminal regions, joints and helium inlets has to take this high voltage into account with sufficient margin, since a failure would mean a major interruption of the Tokamak operation [2].…”

Section: Design Parametersmentioning

confidence: 99%

“…All coils are built by stacking 6 to 9 double-pancake (DP) windings wound with NbTi superconducting cable-in-conduit conductors (CICC) by two-in-hand winding scheme. The outer diameters of the coils vary between 8 m and 24 m. Since the PF coil system provide magnetic fields for plasma shaping and position control with the Central Solenoid (CS) coil, it needs to be pulsed with fast variations of the coil current, leading to induced voltages of up to 14 kV on the coil terminals during operation [2].…”

Section: Introductionmentioning

confidence: 99%

Design of the ITER PF Coils

Lim

Simon

Ilyin

et al. 2011

IEEE Trans. Appl. Supercond.

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ITER magnets are all designed using superconducting conductors with a high current carrying capability. The Poloidal Field (PF) coils are operated in pulsed mode with maximum operating currents of 48 kA for PF 1 and 6, 55 kA for PF 2,3, and 4 and 52 kA for PF 5. The PF system consists of 6 ring coils, PF1 through PF6, that serve to stabilize the position and control the shape of the plasma in the tokamak. The six PF coils are attached to the outside of the Toroidal Field (TF) coil cases through flexible plates or sliding supports allowing radial displacements. The PF coil positions and sizes have been optimized for the plasma requirements consistent with the constraints imposed by allowing access to the vacuum vessel and by considering pumping ducts to the in-vessel components.The PF coils will all be wound with Niobium-Titanium (NbTi) cable-in-conduit conductors (CICC), and range in diameter from 8 m to 24 m. The winding pack consists of stacked double pancakes, with joints only on the outer radius for access/repair and eddy current/AC loss reasons, while the helium inlets are located at the inner radius.Since the 2001 design option, the PF coil windings and their subcomponents have been redesigned to satisfy new operational requirements. The final detailed design has been established in 2009 and validated by the design review held the same year.In this paper, the up-to-date design of the PF coils and each sub-component such as winding pack, electrical insulation, joints and terminations, helium inlet, jumpers, and coils' supports are discussed together with their fabrication methods.

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Reliability Considerations for the ITER Poloidal Field Coils

Cited by 12 publications

References 5 publications

The ITER magnet systems: progress on construction

The ITER magnet systems: progress on construction

Development of the ITER PF Coils

Design of the ITER PF Coils

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