Title :
Energy dissipation in CS model coil joint during normal operation
Author :
Gung, C.Y. ; Seeves, M.M. ; Minervini, J.V.
Author_Institution :
Plasma Fusion Center, MIT, Cambridge, MA, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
The purpose of this work is to provide a tentative data base of heat generated in the joints of ITER CS model coil for further thermohydraulic analysis and design iteration. The present calculation is performed on the basis of normal AC operation of the coil. The DC resistance of a typical model coil joint is estimated to be ~3 nΩ. DC power dissipation at full conductor current of 46 kA is thus 5.9 W. The joint temperature is raised by ~0.1 K when a coolant inlet temperature of 4.5 K with a flowrate of 14 g/s/joint at a pressure of 0.6 MPa is applied. The AC loss in a joint is between 12 and 15 W. The highest total loss estimated at peak conductor current and a maximum current ramp rate is ~20.8 W which causes a temperature rise of ~0.36 K
Keywords :
electric resistance; fusion reactor design; fusion reactor operation; fusion reactors; iterative methods; superconducting coils; superconducting magnets; 0.6 MPa; 3 nohm; 4.5 K; 46 kA; 5.9 W; AC loss; DC power dissipation; DC resistance; central solenoid model coil joint; coolant inlet temperature; design iteration; energy dissipation; fusion reactor; joint temperature; maximum current ramp rate; normal AC operation; peak conductor current; temperature rise; thermohydraulic analysis; Bridges; Cable shielding; Conductors; Coolants; Copper; Energy dissipation; Plasma temperature; Power dissipation; Superconducting cables; Superconducting coils;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534514
