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

A thermo-hydraulic analysis of the superconducting proposal for the TF magnet system of FAST

“…In this regard, assuming that the helium inlet be at the pancake transition located in the outer leg facing the plasma, as suggested by Fig. 1, the thermohydraulic analysis has been carried out with respect to the most critical pancake that is the central one with the longest distance from inlet to equatorial plane [7]. Also, the radial distribution computed in the equatorial plane has been maintained in the other sections by a proper scaling.…”

“…2); in the other case, the effect of heating from casing to WP has been retained into the model. Note that a 2D thermal transient analysis should be carried out in order to quantify the effect of heat transfer from casing to WP and also its time evolution (see for instance [4] or [7]). However, since in the present design the steel casing geometry has not yet been defined, an estimate of the ratio of heat due to casing with respect to heat due to neutrons, and also of the time constant in the exponential decay after the EOB, have been made on the base of the results available in similar analysis [4].…”

4C Code Simulation and Benchmark of ITER TF Magnet Cool-Down From 300 K to 80 K

“…The code has been recently applied to and validated against different types of transients: fast discharge [5], [6], quench propagation [7], temperature margin computation during pulsed operation [8] and pulsed heat load on a SHe circuit [9]. Of special relevance for the present paper, the code was also validated against data from the slow cool-down of a non-planar coil of the W7-X stellarator, obtained during its cold test [10].…”

Modeling of W7-X superconducting coil cool-down using the 4C code

“…In the cold test of a coil, the temperature difference between coolant inlet and outlet is monitored, together with the temperature of the coil casing at three different locations [3], but this measurement cannot obviously guarantee that any two points of the coil satisfy that constraint. In order to verify if this can be an issue, we apply the 4C thermal-hydraulic code [4], recently validated against ITER Toroidal Field Model Coil data for a safety discharge from 25 kA [5], as well as applied to the quench analysis of an ITER TF coil [6] and to the temperature margin prediction in a JT60-SA TF coil [7], to the analysis of the cool-down of an NPC.…”