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 ∼4.4K 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 ∼0.2–0.3K above the design value of 1.2 K.

Computation of JT-60SA TF coil temperature margin using the 4C code / Bonifetto, Roberto; Domalapally, PHANI KUMAR; Polli, G. M.; Savoldi, Laura; Turtu', S.; Villari, R.; Zanino, Roberto. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - STAMPA. - 86:(2011), pp. 1493-1496. [10.1016/j.fusengdes.2011.02.068]

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

BONIFETTO, ROBERTO;DOMALAPALLY, PHANI KUMAR;SAVOLDI, LAURA;ZANINO, Roberto
2011

Abstract

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 ∼4.4K 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 ∼0.2–0.3K above the design value of 1.2 K.
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/11583/2420723
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