Computation of JT-60SA TF coil temperature margin using the 4C code

R. Bonifetto, P.K. Domalapally, G.M. Polli, L. Savoldi Richard, S. Turtu', R. Villari, R. Zanino

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The recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the temperature margin of the superconducting NbTi toroidal field coil of the ITER satellite tokamak JT-60SA, for the nominal burn operation of the machine. Repetitive conditions in the simulation are reached after two plasma pulses. For given (computed) thermal load distribution on winding and coil case due to nuclear heating only, helium temperature ∼4.4 K at the winding inlet, reference strand, and the most recent conductor and winding layout, the computed minimum margin occurs in pancake #7 at the peak field location and turns out to be ∼0.2-0.3 K above the design value of 1.2 K. © 2011 Elsevier B.V. All Rights Reserved.
Original languageEnglish
Pages (from-to)1493 - 1496
Number of pages4
JournalFusion Engineering and Design
Issue number6-8
Publication statusPublished - Oct 2011
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Bonifetto, R., Domalapally, P. K., Polli, G. M., Savoldi Richard, L., Turtu', S., Villari, R., & Zanino, R. (2011). Computation of JT-60SA TF coil temperature margin using the 4C code. Fusion Engineering and Design, 86(6-8), 1493 - 1496.