Thermal-hydraulic stability of the two-channel cable-in-conduit conductors (CICC) foreseen for the central solenoid (CS) and the toroidal field (TF) Nb3Sn super-conducting coils of the International Thermonuclear Experimental Reactor (ITER) is analyzed with the two-fluid code MITHRANDIR [1]. In all external-heating scenarios considered, the computed stability margin is of the order of some 100 mJ/ccst. Extra-strands Cu addition typically leads to higher computed margins. MITHRANDIR estimates are typically conservative with respect to one-fluid results.
机构:
Commissariat Energie Atom & Energies Alternat, CEA IRFM, F-13108 Saint Paul Lez Durance, FranceWest Pomeranian Univ Technol, Fac Mech Engn & Mechatron, Al Piastow 19, PL-70310 Szczecin, Poland
Zani, Louis
Lacroix, Benoit
论文数: 0引用数: 0
h-index: 0
机构:
Commissariat Energie Atom & Energies Alternat, CEA IRFM, F-13108 Saint Paul Lez Durance, FranceWest Pomeranian Univ Technol, Fac Mech Engn & Mechatron, Al Piastow 19, PL-70310 Szczecin, Poland