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

Volume

2

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

1214

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 (ΔB_r21), 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 (ΔB_r21/B_T≈4.5×10^-6 where B_T 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;

fLanguage

English

Publisher

ieee

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

Type

conf

DOI

10.1109/FUSION.1995.534445

Filename

534445