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Predictive 1-D thermal-hydraulic analysis of the prototype HTS current leads for the ITER correction coils.

Author(s) : HELLER R., BAUER P., SAVOLDI L., et al.

Type of article: Article

Summary

We present an analysis of the prototype high-temperature superconducting (HTS) current leads (CLs) for the ITER correction coils, which will operate at 10 kA. A copper heat exchanger (HX) of the meander-flow type is included in the CL design and covers the temperature range between room temperature and 65 K, whereas the HTS module, where Bi-2223 stacked tapes are positioned on the outer surface of a stainless steel hollow cylindrical support, covers the temperature range between 65 K and 4.5 K. The HX is cooled by gaseous helium entering at 50 K, whereas the HTS module is cooled by conduction from the cold end of the CL. We use the CURLEAD code, developed some years ago and now supplemented by a new set of correlations for the helium friction factor and heat transfer coefficient in the HX, recently derived using Computational Fluid Dynamics. Our analysis is aimed first of all at a ‘‘blind” design-like prediction of the CL performance, for both steady state and pulsed operation. In particular, the helium mass flow rate needed to guarantee the target temperature at the HX–HTS interface, the temperature profile, and the pressure drop across the HX will be computed. The predictive capabilities of the CURLEAD model are then assessed by comparison of the simulation results with experimental data obtained in the test of the prototype correction coil CLs at ASIPP, whose results were considered only after the simulations were performed.

Details

  • Original title: Predictive 1-D thermal-hydraulic analysis of the prototype HTS current leads for the ITER correction coils.
  • Record ID : 30021231
  • Languages: English
  • Source: Cryogenics - vol. 80
  • Publication date: 2016/05
  • DOI: http://dx.doi.org/10.1016/j.cryogenics.2016.05.002

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