Conceptual design of superconducting magnet system for JT-60SA

被引:25
作者
Yoshida, K. [1 ]
Kizu, K. [1 ]
Tsuchiya, K. [1 ]
Tamai, H. [1 ]
Matsukawa, M. [1 ]
Kikuchi, M. [1 ]
della Corte, A. [2 ]
Muzzi, L. [2 ]
Turtu, S. [2 ]
Zenobio, A. Di. [2 ]
Pizzuto, A. [2 ]
Portafaix, C. [3 ]
Nicollet, S. [3 ]
Lacroix, B. [3 ]
Decool, P. [3 ]
Duchateau, J-L. [3 ]
Zani, L. [3 ]
机构
[1] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan
[2] ENEA, EURATOM Assoc, Frascati, Italy
[3] CEA, EURATOM Assoc, Cadarache, France
关键词
coil; fusion; JT-60; superconducting; tokamak;
D O I
10.1109/TASC.2008.921970
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
The upgrade of JT-60U magnet system to superconducting coils (JT-60SA) has been decided by both parties of Japanese government (JA) and European commission (EU) in the framework of the Broader Approach (BA) agreement. The magnet system for JT-60SA consists of 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with four modules, seven Equilibrium Field (EF) coils. The TF case encloses the winding pack and is the main structural component of the magnet system. The CS consists of independent winding pack modules, which is hung from the top of the TF coils through its pre-load structure. The seven EF coils are attached to the TF coil cases through supports which include flexible plates allowing radial displacements. The CS modules operate at high field and use Nb3Sn type superconductor. The TF coils and EF coils use NbTi superconductor. The magnet system has a large heat load from nuclear heating from DD fusion and large AC loss. This paper describes the technical requirements, the operational interface and the outline of conceptual design of the superconducting magnet system for JT-60SA.
引用
收藏
页码:441 / 446
页数:6
相关论文
共 16 条
[1]   Nuclear heat, disruption loads and other AC losses and their impact on the ITER toroidal field coils conductor design [J].
Bessette, D ;
Zapretilina, E ;
Shatil, N .
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2000, 10 (01) :1074-1077
[2]  
Briesmeister JF, 2000, MCNP GEN MONTE CARLO
[3]   Design of the ITER-FEAT cryoplant to achieve stable operation over a wide range of experimental parameters and operation scenarios [J].
Claudet, G ;
Kalinine, V ;
Mitchell, N ;
Roussel, P ;
Shatil, N .
FUSION ENGINEERING AND DESIGN, 2001, 58-59 (58-59) :205-209
[4]  
HENRY D, 2007, 2007 CRYOG IN PRESS
[5]   Key engineering features of the ITER-FEAT magnet system and implications for the R&D programme [J].
Huguet, M .
NUCLEAR FUSION, 2001, 41 (10) :1503-1513
[6]  
*ITER, ITER TECHN BAS 2 PLA
[7]  
KIKUCHI M, 2006, 21 IAEA FUS IN PRESS
[8]  
KIZU K, 2007, MT 20 C
[9]  
MATSUKAWA M, 2006, 21 IAEA FUS IN PRESS
[10]   Development of low carbon and boron added 22Mn-13Cr-9Ni-1Mo-0.24N steel (JK2LB) for jacket which undergoes Nb3Sn heat treatment [J].
Nakajima, H ;
Hamada, K ;
Takano, K ;
Okuno, K ;
Fujitsuna, N .
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2004, 14 (02) :1145-1148