Title :
Toroidal field system with demountable multiturn coils for neutron source based on tokamak
Author :
Filatov, O.G. ; Filatov, V.V. ; Korshakov, V.V. ; Kozhukhovskaja, N.M. ; Kuligin, V.S. ; Mikhailov, V.M. ; Panin, A.G. ; Silin, V.P.
Author_Institution :
Efremov (D.V.) Sci. Res. Inst. of Electrophys. Apparatus, St. Petersburg, Russia
Abstract :
A concept of volumetric neutron source (VNS) based on tokamak foresees its high availability, therefore the most simple and reliable technical solutions are required for design of the facility, its systems and units. An electromagnet system with “warm” multiturn coils satisfies these requirements. In this case the power consumption decrease for such systems is one of the main purposes of design development. The VNS magnet system design is associated in many respects with the maximum level of coil material irradiation, which depends on inner radiation shield thickness. The ceramic electric insulation is required for the coils if the shield thickness is less than 0.2 m. The VNS toroidal field system is operated in steady-state mode under high thermal and electromagnetic loads. The coil mechanical stresses obtained is 200-300 MPa, and maximum coil turn temperature is 90-120°C. The copper alloy of Cu-Cr-Zr type is used as a coil conductor material. The general tokamak arrangement and the requirements of simple VNS demountability need electric joints in the toroidal field coil design
Keywords :
ceramic insulation; electromagnets; fusion reactor design; neutron sources; plasma toroidal confinement; 200 to 300 MPa; 90 to 120 C; CuCrZr; VNS magnet system; ceramic electric insulation; coil conductor material; coil mechanical stresses; demountable multiturn coils; electromagnet system; fusion reactors; inner radiation shield thickness; maximum coil turn temperature; steady-state mode; tokamak; toroidal field system; volumetric neutron source; Availability; Coils; Conducting materials; Electromagnets; Energy consumption; Magnetic materials; Magnetic shielding; Neutrons; Power system reliability; Tokamaks;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687035