Engineering design in installation of fully covering ferritic inside wall on JFT-2M

Author

Suzuki, S. ; Tsuzuki, K. ; Kimura, H. ; Kawashima, H. ; Sato, M. ; Yamamoto, M. ; Shibata, T. ; Okano, F. ; Kashiwa, Y. ; Kusama, Y. ; Urata, K. ; Hasegawa, M. ; Sato, F. ; Suzuki, Y.

fYear

2003

fDate

14-17 Oct. 2003

Firstpage

189

Lastpage

192

Abstract

In the JFT-2M tokamak, a low activation ferritic steel, which is a candidate material for a blanket of demo-reactor, has been introduced step by step to investigate the compatibility with plasma. The ferritic plates was installed to cover almost whole inside wall of the vacuum vessel (VV) as a simulate of the blanket wall (ferritic inside wall; FIW). The toroidal field ripple was decreased by adjusting the plate thickness distribution. Prior to the installation, electromagnetic force was calculated. Static force related to ferromagnetism was in the order of 1000 N for each segment (32 pieces in toroidal direction and 7 pieces in poloidal direction). The electromagnetic force is comparable to the static force. The support structure was decided based on this calculation. The most dangerous stress on the support was bending stress. Its maximum value was 170 MPa, which is 2/3 as large as allowable value of M12 bolt. The FIW was installed with a tolerance of a few mm. Tokamak discharges were obtained after the installation and no deteriorative effects have been observed up to now.

Keywords

Tokamak devices; bending; discharges (electric); ferromagnetism; fusion reactor blankets; plates (structures); steel; 170 MPa; JFT-2M tokamak; M12 bolt; bending stress; blanket wall; demo-reactor; deteriorative effects; electromagnetic force calculation; ferritic inside wall; ferritic plates; ferromagnetism; low activation ferritic steel; plate thickness distribution; static force; support structure; tokamak discharges; toroidal field ripple; vacuum vessel; Design engineering; Fasteners; Plasma confinement; Plasma materials processing; Plasma properties; Plasma simulation; Plasma stability; Steel; Tensile stress; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on

Print_ISBN

0-7803-7908-X

Type

conf

DOI

10.1109/FUSION.2003.1426620

Filename

1426620