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

Volume

2

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

1518

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;

fLanguage

English

Publisher

ieee

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

Type

conf

DOI

10.1109/FUSION.1995.534514

Filename

534514