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

Content Provider	IEEE Xplore Digital Library
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.
Copyright Year	2003
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.
Starting Page	189
Ending Page	192
File Size	755997
Page Count	4
File Format	PDF
ISBN	078037908X
DOI	10.1109/FUSION.2003.1426620
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2003-10-14
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Design engineering Steel Tensile stress Plasma confinement Plasma properties Plasma materials processing Plasma stability Tokamaks Fasteners Plasma simulation
Content Type	Text
Resource Type	Article

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