Title :
Electrical and thermal designs and analyses of joints for the ITER PF coils
Author :
Ciazynski, Daniel ; Martinez, André
Author_Institution :
Euratom-CEA Assoc., CEA/CADARACHE, Cadarache, France
fDate :
3/1/2002 12:00:00 AM
Abstract :
The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed with NbTi cable-in-conduit conductors wound in double pancakes which are connected in series by joints. The electrical analysis of these joints includes estimation of the dc resistance, calculation of ac loss power, of loop currents and local Joule heating during the whole plasma scenario. The effect of a plasma disruption is also considered. The thermal analysis is performed using a transient thermohydraulic two-fluid code, modeling the two-channel structure of the cable as well as the counter-flow heat exchanger created in the joint. We show that the CEA twin-box concept using compressed cables inside independent copper-steel boxes is quite usable in all the ITER PF coils. A discussion about possible options (copper RRR) is also presented.
Keywords :
Tokamak devices; cooling; copper; fusion reactor design; fusion reactor ignition; niobium compounds; nuclear engineering computing; plasma ohmic heating; plasma toroidal confinement; steel; superconducting coils; CEA twin-box concept; ITER PF coils; International Thermonuclear Experimental Reactor; NbTi; cable-in-conduit conductors; copper-steel boxes; counter-flow heat exchanger; double pancake windings; electrical design; local Joule heating; loop currents; loss power; plasma disruption; poloidal field coils; resistance; thermal design; transient thermohydraulic two-fluid code; Coils; Conductors; Electric resistance; Inductors; Niobium compounds; Performance analysis; Plasmas; Titanium compounds; Transient analysis; Wounds;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2002.1018461