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Journal Articles

Trial fabrication of one-third scale double pancake of ITER toroidal field coil

Matsui, Kunihiro; Koizumi, Norikiyo; Hemmi, Tsutomu; Takano, Katsutoshi; Nakajima, Hideo; Kimura, Satoshi*; Iijima, Ami*; Sakai, Masahiro*; Osemochi, Koichi*; Shimada, Mamoru*

IEEE Transactions on Applied Superconductivity, 22(3), p.4203005_1 - 4203005_5, 2012/06

 Times Cited Count:7 Percentile:37.82(Engineering, Electrical & Electronic)

JAEA is responsible for the procurement of 9 toroidal field (TF) coils as Japanese Domestic Agency. JAEA had started several trials to successfully develop technologies for the TF coil manufacture since March 2009, and performed one-third scale trials aiming at qualifying and optimizing the procedures of the TF coil fabrication. The fabricated double pancakes (DPs) were successfully put into the profile with tolerances from zero to 1.5 mm. These tolerances correspond to 0.06% accuracy in the conductor length. The geometry of the DP was changed after heat treatment. Heat treatment procedure to avoid such deformation should be developed or the change of winding geometry should be taken into account in the fabrication of the TF coils. The one-third scale DP was successfully impregnated. Although exothermal reaction is given to take place during curing in the blended resin, we successfully cured the one-third scale DP.

Journal Articles

Results of ITER toroidal field coil cover plate welding test

Koizumi, Norikiyo; Matsui, Kunihiro; Shimizu, Tatsuya; Nakajima, Hideo; Iijima, Ami*; Makino, Yoshinobu*

Teion Kogaku, 47(3), p.186 - 192, 2012/03

In the ITER TF coil, cover plates (CP) are welded to teeth of a radial plate (RP) to fix a conductor in the groove of the RP. Though total length of welds is approximately 1.5 km and height and width of an RP are 14 m and 9 m, respectively, the welding deformation better than 1 mm in local distortion and several milli-meters in in-plane deformation is required. Therefore, laser welding is used for the CP welding to reduce welding deformation as possible. However, a gap of a welding joint is expected to be 0.5 mm at the maximum. Therefore, at first, the laser welding technique to enable welding on the gap of 0.5 mm width is developed in this study. Using this technology, CP welding trial using an RP mock was successfully performed. The achieved flatness is 0.6 mm. In addition, the welding deformation of a full-scale RP is estimated by the analysis using the inherent strain. The results show that the flatness of 1 mm is achievable and profile of 5 mm can be achieved. Since the in-plane deformation can be corrected by welding somewhere to originate artificial welding deformation, it is confident that the required tolerance of several milli-meters in in-plan profile is achievable.

Journal Articles

Insulation and impregnation test for ITER toroidal field coils

Hemmi, Tsutomu; Matsui, Kunihiro; Koizumi, Norikiyo; Nakajima, Hideo; Iijima, Ami*; Sakai, Masahiro*

Teion Kogaku, 47(3), p.172 - 177, 2012/03

The manufacturing process for the ITER Toroidal Field (TF) coil has to be demonstrated for the qualification. Since the impregnation of its insulation system is one of the qualifications, the authors performed impregnation test using cyanate-ester and epoxy blended resin, which is a candidate among resins because of its excellent resistance to radiation. To establish the insulation and impregnation procedure of the TF coil manufacturing, three types of trials were performed. (1) Impregnation tests using an acrylic model to fix the impregnation conditions; (2) Impregnation test using a metallic model to confirm that no void remains in the insulation layer after the curing in the D-shaped configuration; and (3) Insulation and impregnation trials using 1/3 scale double pancake (DP) to establish the insulation and impregnation procedure for the TF coil manufacturing, The procedure of the insulation and impregnation for the ITER TF coil was established from the results of these trials.

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