Design and manufacture of a prototype NbTi full-size joint sample for the ITER poloidal field coils

Decool, P.; Ciazynski, D.; Libeyre, P.; Corte, A. della; Spadoni, M.; Rossi, S.; Laurenti, A.; Beaudet, F; Bourquard, A.; Bresson, Daniel

doi:10.1016/s0920-3796(03)00313-2

Cited by 21 publications

(10 citation statements)

References 3 publications

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“…Two heat sources are available on each leg: 1) a resistive heater (OH) is wrapped around an ~ 0.4 m long portion of the conductor jacket with reduced thickness, upstream of T2; 2) a pulsed coil provides a variable magnetic field over a length of ~ 0.39 m inducing AC losses, between T2 and T4. Thick SS clamps (not shown in FIG 1) with epoxy insulation are applied all along the two legs, with the only exception of the temperature sensor locations, and of the OH region [1].…”

Section: Methodsmentioning

confidence: 99%

“…The PF-FSJS [1] was built using two full-size straight conductors (legs), cabled by Europa Metalli and jacketed by Ansaldo, according to the ITER 2-channel (annular cable bundle "B" and central channel "H" regions) cable-in-conduit concept (see FIG 1). The cable is compacted in a thick SS jacket, according to the ITER PF design [2].…”

Section: Introductionmentioning

confidence: 99%

“…Each leg uses NbTi strands with different resistive barrier, leading to different inter-strand resistances and therefore different AC losses. The total length (~ 3.5 m) of each leg includes two terminations: the upper ones (~ 0.6 m long) are used to connect the sample to the independently cooled bus bars of the test facility, while the lower ones (also ~ 0.6 m long) are joined together to close the electric circuit [1]. From the thermal-hydraulic point of view, the two legs are cooled independently with supercritical helium in forced-flow, nominally at 4.5-5.0 K and 0.9-1.0 MPa.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of Thermal-Hydraulic Gravity/ Buoyancy Effects in the Testing of the ITER Poloidal Field Full Size Joint Sample (PF-FSJS)

Zanino¹,

Bruzzone²,

Ciazynski³

et al. 2004

AIP Conference Proceedings

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The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-inconduit conductor (CICC) design currently foreseen for the International Thermonuclear Experimental Reactor (ITER) Poloidal Field coil system. It was tested during the summer of 2002 in the Sultan facility of CRPP at a background peak magnetic field of typically 6 T. It includes about 3 m of two jointed conductor sections, using different strands but with identical layout. The sample was cooled by supercritical helium at nominal 4.5-5.0 K and 0.9-1.0 MPa, in forced convection from the top to the bottom of the vertical configuration. A pulsed coil was used to test AC losses in the two legs resulting, above a certain input power threshold, in bundle helium backflow from the heated region. Here we study the thermal-hydraulics of the phenomenon with the M&M code, with particular emphasis on the effects of buoyancy on the helium dynamics, as well as on the thermal-hydraulic coupling between the wrapped bundles of strands in the annular cable region and the central cooling channel. Both issues are ITER relevant, as they affect the more general question of the heat removal capability of the helium in this type of conductors.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Analysis of Thermal-Hydraulic Gravity/ Buoyancy Effects in the Testing of the ITER Poloidal Field Full Size Joint Sample (PF-FSJS)

Zanino¹,

Bruzzone²,

Ciazynski³

et al. 2004

AIP Conference Proceedings

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“…An additional vacuum furnace heat-treatment at high temperature is achieved to simulate the final heat-treatment of the terminal box prior to cable insertion. This process is implemented for copper softening, facilitating cable compaction into the copper sole (Decool et al, 2003). The temperature in this case is held at 400 • C for 6 hour, subsequent to a ramp-up at 20 • C/hr.…”

Section: Materials and Experimental Proceduresmentioning

confidence: 99%

Extensive Characterisation of Copper-clad Plates, Bonded by the Explosive Technique, for ITER Electrical Joints

Langeslag

Sgobba

Libeyre³

et al. 2015

Physics Procedia

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Cable-in-conduit conductors will be extensively implemented in the large superconducting magnet coils foreseen to confine the plasma in the ITER experiment. The design of the various magnet systems imposes the use of electrical joints to connect unit lengths of superconducting coils by inter-pancake coupling. These twin-box lap type joints, produced by compacting each cable end in into a copper -stainless steel bimetallic box, are required to be highly performing in terms of electrical and mechanical properties. To ascertain the suitability of the first copper-clad plates, recently produced, the performance of several plates is studied. Validation of the bonded interface is carried out by determining microstructural, tensile and shear characteristics. These measurements confirm the suitability of explosion bonded copper-clad plates for an overall joint application. Additionally, an extensive study is conducted on the suitability of certain copper purity grades for the various joint types.

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“…A mockup with the long slot in one side of the conductor has been recently manufactured by CEA [7], which demonstrates its feasibility but no mechanical testing has been performed yet. As far as the joints between conductors of the same double pancake or between adjacent pancakes are concerned, a design derived from that developed by CEA, using twin boxes [8], has been developed (Fig. 4).…”

Section: Manufacture Of Crucial Itemsmentioning

confidence: 99%

Industrial engineering studies for the manufacture of the ITER PF coils

Libeyre

Decool

Guérin

et al. 2007

Fusion Engineering and Design

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Design and manufacture of a prototype NbTi full-size joint sample for the ITER poloidal field coils

Cited by 21 publications

References 3 publications

Analysis of Thermal-Hydraulic Gravity/ Buoyancy Effects in the Testing of the ITER Poloidal Field Full Size Joint Sample (PF-FSJS)

Analysis of Thermal-Hydraulic Gravity/ Buoyancy Effects in the Testing of the ITER Poloidal Field Full Size Joint Sample (PF-FSJS)

Extensive Characterisation of Copper-clad Plates, Bonded by the Explosive Technique, for ITER Electrical Joints

Industrial engineering studies for the manufacture of the ITER PF coils

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