Effective bending strain estimated from Ic test results of a D-shaped Nb3Al CICC coil fabricated with a react-and-wind process for the National Centralized Tokamak

• Published in: Fusion engineering and design Vol. 75-79; pp. 99 - 103
• Main Authors: ANDO, T, KIZU, K, MIURA, Y. M, TSUCHIYA, K, MATSUKAWA, M, TAMAI, H, ISHIDA, S, KOIZUMI, N, OKUNO, K
• Format: Conference Proceeding Journal Article
• Language: English
• Published: Amsterdam Elsevier Science 01.11.2005; New York, NY
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Tokamak; Nuclear fusion reactor; Heat treatment; Nb3Al; Cable-in-conduit conductor (CICC); Bending strain; Critical current (Ic); Research and development
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2005.06.264

Japan National Centralized Tokamak (NCT) is a superconducting tokamak proposed as a modification to JT-60U. As part of the R&D for the National Centralized Tokamak, a two-turn, approximately 2m tall, D-shaped Nb3Al coil was wound and tested using a full-size cable-in-conduit conductor (CICC). The Nb3Al cable-in-conductor was bent following the heat treatment reaction with a maximum bending strain of 0.4% to simulate the react-and-wind fabrication.