Superconducting poloidal field magnet engineering for the ARIES-ST
نویسندگان
چکیده
The critical issues of the poloidal systems for the ARIES-ST design have been presented in this paper. Because of the large plasma current and the need of highly shaped plasmas, the poloidal field (PF) coils should be located inside the toroidal field in order to reduce their current. Even then, the divertor coils carry large currents. The ARIES-ST PF coils are superconducting using the internally cooled cable-in-conduit conductor. The peak self field in the divertor coils is about 15 T and the highest field in the non-divertor coils is about 6 T. The PF magnets have built-in margins that are sufficient to survive disruptions without quenching. The costing study indicates that the specific cost of the PF system is $80/kg. Detailed design and trade-off studies of ARIES-ST are presented and remaining R&D issues are identified. # 2002 Published by Elsevier Science B.V.
منابع مشابه
MgB Coil Options for Fusion Poloidal Magnets
A hybrid solution is proposed for the IGNITOR research fusion machine by using of superconducting coils for some poloidal magnets, in association with high field copper magnets for the central solenoid and for the toroidal field coils. The choice to be made among the various superconductors is based on the materials performances in high magnetic field, on the mechanical strength of the conducto...
متن کاملNuclear performance assessment of ARIES-AT
The transition to a new ARIES design always involves a significant change in the engineering system with emphasis on high performance. Compared to ARIES-RS, numerous improvements were noted in ARIES-AT, ranging from physics improvements to a focus on advanced engineering for an economically and environmentally attractive source of energy. A key engineering aspect of ARIES-AT is its compactness ...
متن کاملUWFDM-1336 Overview of ARIES-CS In-Vessel Components: Integration of Nuclear, Economics, and Safety Constraints in Compact Stellarator
The recent development of the compact stellarator concept delivered ARIES-CS – a compact stellarator with 7.75 m average major radius, approaching that of tokamaks. In stellarators, the most influential engineering parameter that determines the machine size and cost is the minimum distance between the plasma boundary and mid-coil (∆min). Accommodating the breeding blanket and necessary shield w...
متن کاملRelational Database Design for the Test of the Kstar Superconducting Magnet System
The Korea Superconducting Tokamak Advanced Research (KSTAR) superconducting magnet system consists of 16 TF (Toroidal Field) and 14 PF (Poloidal Field) coils. Both of TF and PF coils use internally-cooled conductors. In order to validate the design of the KSTAR TF coil, a full-scale prototype TF coil, TF00, is developed. For the test of TF00, a large scale superconducting magnet and conductor t...
متن کاملUWFDM-1324 Nuclear Challenges and Progress in Designing Stellarator Power Plants
Over the past 2-3 decades, stellarator power plants have been studied in the U.S., Europe, and Japan as an alternate to the mainline magnetic fusion tokamaks, offering steady state operation and eliminating the risk of plasma disruptions. The earlier 1980s studies suggested large stellarators with an average major radius exceeding 20 m. The most recent development of the compact stellarator con...
متن کامل