TY - JOUR
T1 - Design prospect of remountable high-temperature superconducting magnet
AU - Hashizume, Hidetoshi
AU - Ito, Satoshi
N1 - Funding Information:
This work was partially supported by MEXT , Grant-in-Aid for Scientific Research (A), 23246159 , 2011–2013 and MEXT , Grant-in-Aid for Young Scientists (A), 23686132 , 2011–2013. The authors appreciate their students, K. Yagi, T. Yamauchi, Y. Yamamoto, S. Takami, T. Kato, K. Moniwa. T. Sakashita, K. Nara, T. Ohinata, K. Kawai, Y. Tanno, Y. Seino and H. Kaeriyama for collection and analysis of experimental and numerical data. The authors also thank to researchers of NIFS, Y. Yanagi, Y. Terazaki, K. Natsume, S. Hamaguchi, H. Noguchi, H. Tamura, T. Mito, A. Sagara and researchers of PSFC, MIT, L. Bromberg, M. Takayasu and J. V. Minervini for technical support and valuable comments in the mechanical joint experiment of HTS conductor samples.
PY - 2014/10
Y1 - 2014/10
N2 - The remountable (mountable and demountable repeatedly) high-temperature superconducting (HTS) magnet has been proposed for huge and complex superconducting magnets in future fusion reactors to fabricate and repair easily the magnet and access inner structural components. This paper summarizes progress in R&D activities of mechanical joints of HTS conductors in terms of the electrical resistance and heat transfer performance at the joint region. The latest experimental results show the low joint resistance, 4 nΩ under 70 kA current condition using REBCO HTS conductor with mechanical lap joint system, and for the cooling system the maximum heat flux of 0.4 MW/m2 is removed by using bronze sintered porous media with sub-cooled liquid nitrogen. These values indicate that there is large possibility to design the remountable HTS magnet for fusion reactors.
AB - The remountable (mountable and demountable repeatedly) high-temperature superconducting (HTS) magnet has been proposed for huge and complex superconducting magnets in future fusion reactors to fabricate and repair easily the magnet and access inner structural components. This paper summarizes progress in R&D activities of mechanical joints of HTS conductors in terms of the electrical resistance and heat transfer performance at the joint region. The latest experimental results show the low joint resistance, 4 nΩ under 70 kA current condition using REBCO HTS conductor with mechanical lap joint system, and for the cooling system the maximum heat flux of 0.4 MW/m2 is removed by using bronze sintered porous media with sub-cooled liquid nitrogen. These values indicate that there is large possibility to design the remountable HTS magnet for fusion reactors.
KW - Cryogenic coolant
KW - Heat transfer enhancement
KW - High-temperature superconductor
KW - Mechanical joint
KW - Porous media
KW - Superconducting magnet
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U2 - 10.1016/j.fusengdes.2013.12.014
DO - 10.1016/j.fusengdes.2013.12.014
M3 - Article
AN - SCOPUS:84905969125
VL - 89
SP - 2241
EP - 2245
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 9-10
ER -