Conductor design of CS and EF coils for JT-60SA
Creators
- 1. Japan Atomic Energy Agency, Ibaraki 311-0193, (Japan)
- 2. EURATOM-ENEA Assoc., 00044 Frascati, Rome, (Italy)
- 3. CEA Cadarache, DSM, DRFC, EURATOM-CEA Assoc., F-13108 Saint Paul lez Durance, (France)
Description
The conductor for central solenoid (CS) and equilibrium field (EF) coils of JT-60 Super Advanced (JT-60SA) were designed. The conductor for CS is Nb3Sn Cable-In-Conduit (CIC) conductor with JK2LB jacket. EF coil conductors are NbTi CIC conductor with SS316LN jacket. The field change rate (3.9 T/s), faster than ITER generates the large AC loss in conductor. The analyses of current sharing temperature (Tcs) margins for these coils were performed by the one-dimensional fluid analysis code with transient heat loads. The Tcs margins of these coils are ≥ 1 K for the plasma standard and disruption scenarios. The minimum T,, margin of CS conductor is 1.2 K at plasma break down (BD). The margin is increased by decreasing the rate of initial magnetization. It is found that the disruption mainly impacts the outer low field EF coil. The disruption decreases the Tcs margin of the coil by ≥1 K. A coupling time constant of ≤ 100 ms, Ni plating, and a central spiral are required for NbTi conductor. (authors)
Availability note (English)
Available from doi:Additional details
Identifiers
Publishing Information
- Journal Title
- IEEE Transactions on Applied Superconductivity (Print)
- Journal Volume
- 18
- Journal Issue
- no.2
- Journal Page Range
- p. 212-215
- ISSN
- 1051-8223
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 41034496
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- AC LOSSES; BREAKDOWN; DESIGN; JT-60 TOKAMAK; MAGNET COILS; PLASMA DISRUPTION; SUPERCONDUCTING COILS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ENERGY LOSSES; EQUIPMENT; LOSSES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Notes
- 9 refs.