Abstract
Joints are essential components of poloidal field coil in fusion device, serving as an electric and coolant transfer between adjacent superconductors. The design of full size joint sample has been carried out by ASIPP. In the future, this sample will be tested in the Sultan facility at Villigen. The test contents include joint total resistance at 4.2 K and 55 kA with 2 T external field, and AC losses at 4.2 K and 45 kA with an external field varying from 0 to 2 T in 1 s. This paper mainly describes the design and analysis of full size joint sample. This sample is composed of two single conductor legs, a praying-hand joint to be placed in the high field, and two terminals to be connected to the transformer of the test facility. The temperature sensors and voltage taps are used for measuring and calculating the DC resistance and AC loss. In order to support the design, the electromagnetic and mechanical analyses are performed. According to the electromagnetic and mechanical analyses, the results show that this design is feasible.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
F. Simon, C. Boyer, Y. Ilyin, C. Beemsterboer, B.S. Lim, Design of the ITER PF coil joints. IEEE Trans. Appl. Supercond. 22, 4804104 (2012)
F. Simon, Y. Ilyin, B.S. Lim, F. Cau, R. Herzog, B. Stepanov, Reliability considerations for the ITER poloidal field coils. IEEE Trans. Appl. Supercond. 20, 423–426 (2010)
P. Decool, D. Ciazynski, P. Libeyre, A. Della Corte, M. Spadoni, S. Rossi et al., Design and manufacture of a prototype NbTi full-size joint sample for the ITER poloidal field coils. Fusion Eng. Des. 66–68, 1165–1169 (2003)
V.I. Bondarenko, B.I. Egorov, Y.A. Klimchenko, O.A. Kovalchuk, E.L. Marushin, A.A. Mednikov et al., Technology and tooling to manufacture low-ohm (<2 nΩ) electrical joints of the ITER PF1 coil. IEEE Trans. Appl. Supercond. 23, 4201605 (2013)
B. Stepanov, P. Bruzzone, M. Vogel, A low cost joint for the ITER PF coils, design and test results. Fusion Eng. Des. 75–79, 259–263 (2005)
R. Zanino, M. Bagnasco, F. Bellina, P. Gislon, P.L. Ribani, L.S. Richard, Modeling AC losses in the ITER NbTi poloidal field full size joint sample (PF-FSJS) using the THELMA code. Fusion Eng. Des. 75–79, 23–27 (2005)
F.H. Hurd, C. Sborchia, E. Salpietro, D. Duglue, C. Keefe, S. Bates et al., Design and manufacture of a full size joint sample (FSJS) for the qualification of the poloidal field (PF) insert coil. IEEE Trans. Appl. Supercond. 15, 1379 (2005)
P. Decool, D. Ciazynski, A. Nobili, S. Parodi, P. Pesenti, A. Bourquard et al., Joints for large superconducting conductors. Fusion Eng. Des. 58–59, 123–127 (2001)
D. Ciazynski, P. Decool, M. Rubino, J.M. Verger, N. Valle, R. Maix, Fabrication of the first European full-size joint sample for ITER (ASC, Palm Desert, CA, 1998)
User specification for conductor samples to be tested in the Sultan facility, Section 2 (CRPP, Villigen, Switzerland, 2002)
M. Bagnasco, Calorimetric method for current sharing temperature measurements in ITER conductor samples in SULTAN. Fusion Eng. Des. 84, 423–426 (2009)
Acknowledgments
This work is supported by the National Natural Science Foundation of China (No. 51177164). The authors of this paper deeply appreciate all the members of PF6 team for their hard work and beneficial discussion.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Yao, Y., Song, Y.T., Wu, H. et al. Design and Analysis of Full Size Joint Sample for ITER PF Coil. J Fusion Energ 34, 802–807 (2015). https://doi.org/10.1007/s10894-015-9885-8
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-015-9885-8