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Oral presentation

Performance of mass-produced superconductor for ITER central solenoid

Nabara, Yoshihiro; Suwa, Tomone; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Evaluation of critical current for JT-60SA central solenoid model coil

Murakami, Haruyuki; Kizu, Kaname; Natsume, Kyohei; Tsuchiya, Katsuhiko; Koide, Yoshihiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Chikaraishi, Hirotaka*; et al.

no journal, , 

no abstracts in English

Oral presentation

Twist pitch distribution in the Central Solenoid cable during insertion into the conduit

Suwa, Tomone; Nabara, Yoshihiro; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Shibutani, Kazuyuki*; Sekiguchi, Nobuo*; Matsuda, Hidemitsu*

no journal, , 

no abstracts in English

Oral presentation

Design and development of the current feeding system for superconducting coils of JT-60SA

Kizu, Kaname; Murakami, Haruyuki; Natsume, Kyohei; Tsuchiya, Katsuhiko; Koide, Yoshihiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Hamaguchi, Shinji*; Takahata, Kazuya*

no journal, , 

The current feeding system for superconducting magnets of JT-60SA were designed. Key components concerned were developed and tested. Trial manufacturing of crank shaped feeder to reduce the thermal stress showed the max. dimensional error of 3 mm. The compact tool to connect the feeder joint with solder vertically was developed. The joint resistance of feeder joint sample was 2n $$Omega$$ within the requirement of $$<$$ 5n$$Omega$$. Feeder insulation samples showed sufficient shear strength. Since all the manufacturing processes concerned were confirmed, the production of CTBs and feeders can be started.

Oral presentation

Manufacturing and assembly status of superconducting magnet components for the JT-60SA

Yoshida, Kiyoshi; Kizu, Kaname; Tsuchiya, Katsuhiko; Murakami, Haruyuki; Honda, Atsushi; Kashiwa, Yoshitoshi; Koide, Yoshihiko; Usui, Katsutomi; Natsume, Kyohei

no journal, , 

The upgrade of the JT-60U magnet system to the superconducting coils (JT-60SA) is progressing as a satellite facility for ITER by both parties of Japanese government and European commission (EU) in the Broader Approach agreement. Three equilibrium field coils were installed in the cryostat base before assembly of plasma vacuum vessel. This report shows the Manufacturing and assembly status of superconducting magnet components for the JT-60SA.

Oral presentation

Progress of ITER toroidal field coil procurement

Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; Takano, Katsutoshi; Ando, Shinji; Yamane, Minoru; Mizutani, Takumi; Nakano, Toshihide; Katayama, Kenji; Iguchi, Masahide; et al.

no journal, , 

no abstracts in English

Oral presentation

Thermometer attachment methods on a helium pipe for JT-60SA

Natsume, Kyohei; Murakami, Haruyuki; Yanagi, Shunki; Kizu, Kaname; Yoshida, Kiyoshi

no journal, , 

Valve Boxes (VBs) and Coil Terminal Boxes (CTBs) will be fabricated as magnet shared components and be installed on the cryostat of JT-60SA. VB is for distributing cryogens to superconducting magnets, cryopumps, and thermal shields. CTB includes the interface between high temperature superconducting current leads and power supply bus bars. In this presentation, attachment methods of thermal sensors on the cryogen pipes in vacuum VB or CTB are described. An Experiment to measure the helium in the pipe has been conducted using the two different attachment methods. The experimental results are compared and estimated by considering measurement accuracy and productivity.

Oral presentation

ITER TF progress of coil cover plate welding trial

Ando, Shinji; Takano, Katsutoshi; Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; Koizumi, Norikiyo

no journal, , 

In a toroidal magnetic field (TF) coil winding part, the double pancake (DP) is produced by inserting a superconduction conductor in the stainless steel board with the groove of the D form called radial plate (RP) and covering plate called the cover plate (CP) and welding RP and CP. This DP with 13m in height, 9m in width, a large structure of thickness 10cm is required to be producted with high accuracy of flatness 2mm. Therefore, JAEA decided a welding condition by the welding quality confirmation examination that was highly precise and was rational at CP welding, and examined full scale mockup trial and obtained a result of 0.8mm to satisfy lower than required precision 2mm of the flatness. Furthermore, the trial manufacture examination of the dummy DP was started to perform inspection in the actual machine D shape size and report the progress.

Oral presentation

Status of radial plate Manufacture for ITER TF Coil

Takano, Katsutoshi; Ando, Shinji; Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; Koizumi, Norikiyo

no journal, , 

The radial plates (RP), which is used in Toroidal field (TF) coil in ITER, are quite large, such as 13 m tall and 9 m wide, but thin, such as 10 cm thick. Even though they are very large structures, high manufacturing tolerances required. The authors therefore performed trial manufacture of full-scale RP. As a result of trials, it was highly accurate RP manufacturing method was able to be proven. In addition, actual RP production is advanced based on full-scale RP manufacture result. In this announcement, it is a report about the progress of a result and the actual RP production of the full-scale trial manufacture.

Oral presentation

Results of winding trial and manufacturing developments for ITER TF coil

Kajitani, Hideki; Hemmi, Tsutomu; Mizutani, Takumi; Matsui, Kunihiro; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo

no journal, , 

JAEA is charging on procurement of 9 TF coils in ITER project. To meet the schedule of ITER project, TF coils should be fabricated in 2 manufacturing lines. In the TF coil winding production, the conductor should be inserted the radial plate (RP) groove after its D shape winding and heat treatment. To insert the conductor into RP groove correctly, the conductor length should be controlled within the error of $$pm$$0.01%. To achieve this high accuracy winding system, the winding system using laser marker and CCD camera to measure conductor length was developed and then the winding trials had been performed using this system. As a result, high accuracy winding could be achieved.

Oral presentation

Transient heat transfer from a wire inserted into a vertically mounted pipe to forced-flow subcooled liquid hydrogen

Tatsumoto, Hideki; Shirai, Yasuyuki*; Shiotsu, Masahiro*; Horie, Yuki*; Yoneda, Kazuya*; Matsuzawa, Takayuki*; Kobayashi, Hiroaki*; Naruo, Yoshihiro*; Inatani, Yoshifumi*

no journal, , 

no abstracts in English

Oral presentation

Development of a splittable accumulator with pressure-tolerance for the cryogenic hydrogen system at J-PARC

Otsu, Kiichi; Tatsumoto, Hideki; Aso, Tomokazu; Kawakami, Yoshihiko

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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