Article

Electrical and thermal designs and analyses of joints for the ITER PF coils

Euratom-CEA Assoc., CEA/CADARACHE, Cadarache
IEEE Transactions on Appiled Superconductivity (impact factor: 1.04). 04/2002; DOI:10.1109/TASC.2002.1018461 pp.538 - 542
Source: IEEE Xplore

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.

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Keywords

ac loss power
 
CEA twin-box concept
 
compressed cables
 
copper RRR
 
electrical analysis
 
independent copper-steel boxes
 
International Thermonuclear Experimental Reactor
 
ITER
 
ITER PF coils
 
joints
 
local Joule heating
 
PF
 
thermal analysis
 
transient thermohydraulic two-fluid code
 
two-channel structure
 

D. Ciazynski