Design, Manufacture, and Test of an 80 kA-Class Nb3Sn Cable-In-Conduit Conductor With Rectangular Geometry and Distributed Pressure Relief Channels

Muzzi, L.; Affinito, L.; Chiarelli, S.; Corato, V.; Corte, A. della; Zenobio, A. Di; Freda, R.; Turtù, S.; Anemona, A.; Righetti, Riccardo; Bragagni, A.; Seri, M.; Gabiccini, F.; Roveta, G.; Aveta, Antonio; Galignano, Stefano; Bruzzone, Pierluigi; Sedlák, Kamil; Stepanov, B.; Wesche, R.

doi:10.1109/tasc.2016.2627539

Cited by 44 publications

(49 citation statements)

References 20 publications

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“…Available correlations, widely used for the assessment of the ITER conductor performance, as well as for the design of the new generation of superconducting CICCs like those for future DEMO reactors, proved to be capable to reproduce the measured pressure drop with an accuracy better than 20% for the conductors where the hole is delimited with a flat spiral as in the ITER conductors or foreseen for instance for some options of the EU DEMO conductors [11].…”

Section: Discussionmentioning

confidence: 99%

Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns

Brighenti

Bonifetto

Isono

et al. 2017

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract. The ITER Central Solenoid Model Coil (CSMC) is a superconducting magnet, layer-wound two-in-hand using Nb 3 Sn cable-in-conduit conductors (CICCs) with the central channel typical of ITER magnets, cooled with supercritical He (SHe) at ~4.5 K and 0.5 MPa, operating for approximately 15 years at the National Institutes for Quantum and Radiological Science and Technology in Naka, Japan. The aim of this work is to give an overview of the issues related to the hydraulic performance of the three different CICCs used in the CSMC based on the extensive experimental database put together during the past 15 years. The measured hydraulic characteristics are compared for the different test campaigns and compared also to those coming from the tests of short conductor samples when available. It is shown that the hydraulic performance of the CSMC conductors did not change significantly in the sequence of test campaigns with more than 50 cycles up to 46 kA and 8 cooldown/warmup cycles from 300 K to 4.5 K. The capability of the correlations typically used to predict the friction factor of the SHe for the design and analysis of ITER-like CICCs is also shown.

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Section: Discussionmentioning

confidence: 99%

Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns

Brighenti

Bonifetto

Isono

et al. 2017

IOP Conf. Ser.: Mater. Sci. Eng.

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“…The total number of turns is 202, with a conductor operating current of I op =70.8 kA at 4.5 K and 12.3 T. The approach to the design of the cables is represented in Fig. 5(c) [16]: the segregated copper is either distributed within the cable bundle, with 1 mm diameter wires, or within the cores of the petals (C1), with 1.5 mm diameter wires, or within the overall cable core (C2), again with 1.5 mm diameter wires. The cable is formed with six petals around core C2, but two out of the six petals have a spiral (low-impedance cooling channels) as a core.…”

Section: Tf Wp#2 Designmentioning

confidence: 99%

“…To demonstrate the technological feasibility of large-size, high current conductors relevant to DEMO magnets, a short-length sample was manufactured and tested in the EDIPO facility [16]. The Cable-in-Conduit Conductor (CICC) was designed to satisfy the 2013 reference baseline [5], i.e.…”

Section: Tf Wp#2 Designmentioning

confidence: 99%

Progress in the design of the superconducting magnets for the EU DEMO

Corato

Bagni

Biancolini

et al. 2018

Fusion Engineering and Design

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In the framework of the DEMOnstration fusion power plant (DEMO) design coordinated by the EUROfusion consortium, a pre-conceptual design of the superconducting magnet system has been developed. For the toroidal field coils (TFCs), three winding pack (WP) options have been proposed; exploring different winding approaches (pancakes vs. layers), and manufacturing techniques (react & wind vs. wind & react Nb 3 Sn). Thermal-hydraulic and mechanical analyses on the three WPs have produced encouraging results, with some critical issues to be solved in future studies and optimizations. The experimental tests on TF prototype short sample conductors have demonstrated a limited performance degradation with electromagnetic cycles and significantly lower effective strains than most of the large-size Nb 3 Sn conductors reported in literature. The toroidal field quench protection circuit has been studied, starting from different topologies and focusing on the most promising one. Two designs are also presented for the central solenoid magnet, with preliminary evaluations on the AC losses during the plasma breakdown. Finally, the design of a TF winding pack based on HTS conductors and the experimental tests on "fusion-relevant" HTS cables are illustrated.

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“…The Nb 3 Sn strands used in the WP2 sample is produced by WST (Western Superconducting Technologies, Xian, China) using the internal Sn technology and has a diameter of 1 mm [107], see Figure 6.14. The scaling law parameters for the critical current, following eq.…”

Section: Rectangular Tf Wp2 Conductormentioning

confidence: 99%

“…The absence of the initial slope at low frequency in the EDIPO total loss does not allow a direct extrapolation of the hysteresis loss. The WST strand of 1.0 mm diameter used for the ENEA conductor has the same internal geometry as the ITER TF WST strand with 0.82 mm diameter [107]. Therefore, an estimate of the hysteresis loss of the WP2 sample can be derived from the ITER strand AC loss data.…”

Section: Wp2 Hysteresis Loss Analysis Of Edipo Measurementsmentioning

confidence: 99%

Modeling electro-magnetic and thermal Stability of Cable-in-Conduit Superconductors for Fusion Magnets

Bagni

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The views and the opinions expressed herein do not necessarily reflect those of the ITER Organization as well as EUROFusion. vi vii per mio padre to my father viii xix 5.4. JackPot Plasma Scenario short sample simulation _____________ 5.4.1. Magneto-resistance and Lorentz' force effect ___________________ 5.4.2. Simulation results ________________________________________ 5.5. Temperature evolution in a layer of CSU2 module ____________ 5.5.1. JaskPot-THEA results ______________________________________ 5.6. Conclusion ____________________________________________

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Design, Manufacture, and Test of an 80 kA-Class Nb3Sn Cable-In-Conduit Conductor With Rectangular Geometry and Distributed Pressure Relief Channels

Cited by 44 publications

References 20 publications

Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns

Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns

Progress in the design of the superconducting magnets for the EU DEMO

Modeling electro-magnetic and thermal Stability of Cable-in-Conduit Superconductors for Fusion Magnets

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