Title :
Error field analysis of steady state tokamak reactor with ferromagnetic (F82H) blanket
Author :
Takeji, S. ; Mori, M. ; Kikuchi, M. ; Ninomiya, H. ; Jitsukawa, S. ; Itoh, T. ; Kuriyama, M. ; Kishimoto, H.
Author_Institution :
Naka Fusion Res. Establ., JAERI, Ibaraki, Japan
fDate :
30 Sep-5 Oct 1995
Abstract :
Error fields generated by a ferromagnetic steel (reduced activation ferritic steel: F82H) blanket were estimated in a conceptual design of the steady state tokamak reactor. The amplitude of radial error field with the poloidal mode number=2 and the toroidal mode number=1 (ΔBr21), which results in locked mode disruptions, was about 0.4 G at the plasma surface, while the maximum radial error field was about 600 G at the port edges. The relative error field (ΔBr21/BT≈4.5×10-6 where BT is the toroidal field of 9T) was comparable with the predicted critical relative error field for locked modes
Keywords :
ferromagnetic materials; fusion reactor blankets; fusion reactor design; fusion reactors; steel; F82H blanket; conceptual design; critical relative error field; error field analysis; ferromagnetic blanket; ferromagnetic steel; locked mode disruptions; maximum radial error field; plasma surface; port edges; reduced activation ferritic steel; steady state tokamak reactor; Error analysis; Inductors; Laser mode locking; Magnetic shielding; Plasma confinement; Plasma properties; Plasma stability; Steady-state; Steel; Toroidal magnetic fields;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534445