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

IEEE Transactions on Applied Superconductivity

Volumn 12, Issue 1, 2002, Pages 538-542

  Ciazynski, Daniel ^a   Martinez, André ^a  

^a IRFM   (France)

Author keywords

Cable in conduit; Electrical joints; ITER; Nuclear fusion; PF coils

Indexed keywords

CALCULATIONS; ELECTRIC CONDUITS; ELECTRIC CURRENTS; ELECTRIC LOSSES; ELECTRIC NETWORK ANALYSIS; ELECTRIC RESISTANCE; HEAT EXCHANGERS; MAGNETIC FIELDS; NIOBIUM COMPOUNDS; NUCLEAR REACTORS; THERMOANALYSIS; UNIVERSAL JOINTS;

CABLE-IN-CONDUIT CONDUCTOR; ELECTRICAL JOINTS; INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR; JOULE HEATING; PLASMA DISRUPTION; POLOIDAL FIELD COILS; TRANSIENT THERMOHYDRAULIC;

SUPERCONDUCTING CABLES;

EID: 0036509656     PISSN: 10518223     EISSN: None     Source Type: Journal    
DOI: 10.1109/TASC.2002.1018461     Document Type: Conference Paper

References (12)

1. ITER final design report July 2001
2. Large superconductors and joints for fusion magnets: From conceptual design to testing at full scale
3. Joints for large superconducting conductors
4. Fabrication of the first European full-size joint sample for ITER
5. Development of joints in Europe for the ITER TFMC
6. NbTi superconducting busbars for the ITER TFMC
7. Task M50: Manufacture and testing of subsize joint samples
8. Effect of actual cabling pattern on the critical current of a multistage cable-in-conduit
9. Characterization of transport properties variations with magnetic field and temperature of ITER-candidate NbTi strands
10. EFDA contract 00/541: ITER PF coils design and analysis
11. Circulating currents in the superconducting joints of the NET model coil and related phenomena
12. Dual channel cable in conduit thermohydraulics: Analysis of the European full size joint samples test results