Manufacture and Quality Control of Insert Coil with Real ITER TF Conductor

Journal Article · Wed Mar 02 00:00:00 EST 2016 · IEEE Transactions on Applied Superconductivity

DOI:https://doi.org/10.1109/TASC.2016.2537150· OSTI ID:1376313

Ozeki, H. ^[1]; Isono, T. ^[1]; Uno, Y. ^[1]; Kawano, K. ^[1]; Kawasaki, T. ^[1]; Ebisawa, N. ^[1]; Okuno, K. ^[1]; Kido, S. ^[2]; Semba, T. ^[2]; Suzuki, Y. ^[2]; Ichimura, T. ^[2]; Inoue, S. ^[2]; Kuchiishi, Y. ^[2]; Hasegawa, H. ^[2]; Smirnov, A. ^[3]; Martovetsky, Nicolai ^[3]

---

1. Japan Atomic Energy Agency, Tokai (Japan)
2. Hitachi, Ibaraki (Japan)
3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

JAEA successfully completed the manufacture of the toroidal field (TF) insert coil (TFIC) for a performance test of the ITER TF conductor in the final design in cooperation with Hitachi, Ltd. The TFIC is a single-layer 8.875-turn solenoid coil with 1.44-m diameter. This will be tested for 68-kA current application in a 13-T external magnetic field. TFIC was manufactured in the following order: winding of the TF conductor, lead bending, fabrication of the electrical termination, heat treatment, turn insulation, installation of the coil into the support mandrel structure, vacuum pressure impregnation (VPI), structure assembly, and instrumentation. Here in this presentation, manufacture process and quality control status for the TFIC manufacturing are reported.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1376313
• Journal Information: IEEE Transactions on Applied Superconductivity, Vol. 26, Issue 4; ISSN 1051-8223
• Publisher: Institute of Electrical and Electronics Engineers (IEEE)
• Country of Publication: United States
• Language: English

Related Subjects

75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
central solenoid (CS) model coil
ITER
toroidal field (TF) coil
toroidal field (TF) conductor
TF insert coil