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Journal Articles

Development of ITER TF coil in Japan

Koizumi, Norikiyo; Matsui, Kunihiro; Hemmi, Tsutomu; Takano, Katsutoshi; Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo; Shimada, Mamoru*; Osemochi, Koichi*; Makino, Yoshinobu*; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4200404_1 - 4200404_4, 2012/06

 Times Cited Count:9 Percentile:47.58(Engineering, Electrical & Electronic)

JAEA started sub- and full-scale trials to qualify and optimize manufacturing procedure of ITER TF coil from March, 2009. As major outcome of these trials, automatic winding system with accuracy in conductor length measurement of 0.01% has been established and the elongation of the conductor length due to heat treatment was measured to be 0.06%. To confirm validity of these outcomes, the authors carried out winding of a one-third scale dummy double pancake (DP), followed by its insulation and impregnation trial, and, in addition, heat treatment of one-third scale DP with real a TF conductor. The details about these trials are described in the other paper. The authors also performed trial manufacture of full scale RP and CPs for dummy double pancake, which will be made in near future. The full scale RP is manufactured by machining 10 segments in parallel to shorten machining duration and joining each segment by welding. In our trial manufacture of the full scale RP, hot-rolled SS316LN plates are machined to a final dimension, namely without additional material, and these segments are laser-welded. From these trials, manufacturing procedure of a thick hot-roll SS316LN plate is qualified and machining procedure is established, while more optimization may be necessary to achieve the required schedule and cost.

Journal Articles

Trial manufacture of ITER toroidal field coil radial plate

Takano, Katsutoshi; Koizumi, Norikiyo; Shimizu, Tatsuya; Nakajima, Hideo; Esaki, Koichi*; Nagamoto, Yoshifumi*; Makino, Yoshinobu*

Teion Kogaku, 47(3), p.178 - 185, 2012/03

In the ITER TF coil, the tight tolerances of 1 mm in flatness and a few mm in profile are required in manufacturing a radial plate (RP), although the height and width of an RP are 13 m and 9 m, respectively. In addition, since cover plates (CP) should be fitted to a groove of an RP with tolerance of 0.5 mm, the tight tolerances are also required to a CP. Thus, we can conclude that the manufacturing procedure of the RP and CP has been demonstrated.

Journal Articles

Study of ITER toroidal field coil manufacturing procedure

Nagamoto, Yoshifumi*; Osemochi, Koichi*; Shimada, Mamoru*; Senda, Ikuo*; Koizumi, Norikiyo; Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo

Teion Kogaku, 47(3), p.200 - 205, 2012/03

Based on the results of the sub- and full-scale trials, the TF coil and TF coil structure manufacturing procedures were considered. Radial plate (RP) will be manufactured by assembling 10 sets of segments with Laser Beam Welding. Cover plates (CPs) will be manufactured by 3 different methods, depending on their geometry. For Winding pack (WP), winding system to enable to measurement of the conductor length with the accuracy of 0.01% for serial production was designed. Assembling procedure and groove types of narrow gap TIG welding for coil structures were determined. Hereafter, technical improvements will be considered in order to aim for further optimization of manufacturing.

Oral presentation

Laser welding of radial plate for ITER TF coil

Makino, Yoshinobu*; Goto, Yu*; Kanahara, Toshio*; Nagamoto, Yoshifumi*; Osemochi, Koichi*; Koizumi, Norikiyo; Takano, Katsutoshi; Matsui, Kunihiro; Nakajima, Hideo

no journal, , 

The toroidal field coil is manufactured as one of superconducting coil systems in the ITER. For welding the radial plate of TF coil, the prevention of the welding deformation and the high quality of the joints among the radial plates are required. Moreover, the application of high efficient welding is required in consideration for the productivity. Therefore, 10kW high power laser welding process was investigated for the application to the radial plate welding, because its process is superior in the productivity for the joints and the ease of the control for the heat input. In the experiment, it was confirmed that the application of the high power laser welding with the 6 axes industrial robots is effective in the welding deformation less than approximately 0.5mm for the small model. Finally, the effectiveness of the laser welding for the welding deformation and the weldability on the quality was verified by the real scale test with the actual shape.

Oral presentation

Laser welding of radial plate for ITER TF coil

Makino, Yoshinobu*; Goto, Yu*; Kanahara, Toshio*; Nagamoto, Yoshifumi*; Osemochi, Koichi*; Koizumi, Norikiyo; Takano, Katsutoshi; Matsui, Kunihiro; Nakajima, Hideo

no journal, , 

no abstracts in English

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