著者

辺見 努 松井 邦浩 小泉 徳潔 中嶋 秀夫 飯島 亜美 酒井 正弘

出版者

公益社団法人 低温工学・超電導学会 (旧 社団法人 低温工学協会)

雑誌

低温工学 (ISSN:03892441)

巻号頁・発行日

vol.47, no.3, pp.172-177, 2012-03-25 (Released:2012-07-04)

参考文献数

6

被引用文献数

3 3

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The manufacturing process for ITER toroidal field (TF) coils must be demonstrated as effective in order to meet the criteria for qualification. Since impregnation of the insulation system is one criterion for qualification in this study, we performed impregnation tests using a cyanate-ester/epoxy blended resin, chosen for its excellent resistance to radiation. To establish the insulation and impregnation procedure in the TF coil manufacturing process, three types of trials were performed: 1) impregnation tests using an acrylic model to fix the impregnation conditions; 2) an impregnation test using a metallic model to confirm that no void remains in the insulation layer after curing in the D-shaped configuration; and 3) insulation and impregnation trials using a 1/3-scale double-pancake (DP) model. The results of these trials were used to determine the insulation and impregnation procedures for manufacturing ITER TF coils.

著者

井口 将秀 千田 豊 中嶋 秀夫 小川 剛史 片山 義紀 小方 大成 峯村 敏幸 宮部 圭介 渡海 大輔 新見 健一郎

出版者

公益社団法人 低温工学・超電導学会 (旧 社団法人 低温工学協会)

雑誌

低温工学 (ISSN:03892441)

巻号頁・発行日

vol.47, no.3, pp.193-199, 2012-03-25 (Released:2012-07-04)

参考文献数

11

被引用文献数

5 2

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The Japan Atomic Energy Agency (JAEA) has conducted activities in Japan since March 2009 in order to establish the manufacturing procedure for the ITER toroidal field (TF) coil structures. A TF coil structure consists of a TF coil case and components. The activities include ensuring that the structural materials and welding procedure comply with the Japan Society of Mechanical Engineers (JSME) code for fusion devices, and demonstrating the manufacturing method and procedures using full-scale segments of the TF coil structure. From the results of these activities, the JAEA confirmed that the quality control method of actual series TF coil structures complies with the JSME code. Therefore, the quality of structural materials and weld joints using gas tungsten arc welding (GTAW) satisfy the ITER requirements. In addition, the JAEA obtained knowledge regarding the welding deformation of the actual TF coil structures. This paper describes the results of these compliance and development activities for ITER TF coil structures.

著者

進藤 裕英 小堀 智之 堀口 勝三 山田 英一 中嶋 秀夫 辻 博史

出版者

公益社団法人 日本金属学会

雑誌

日本金属学会誌 (ISSN:00214876)

巻号頁・発行日

vol.59, no.8, pp.793-798, 1995 (Released:2008-04-04)

参考文献数

12

被引用文献数

2

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This paper discusses fracture toughness and temperature rise for JJ1 austenitic stainless steel forged plate at liquid helium temperature for fusion reactor magnets of next generation. Elastic-plastic fracture toughness (JIC) testing was conducted in general accordance with ASTM standards E813-81 and E813-87, and unloading-compliance technique was applied using compact specimens 25.0 mm and 12.5 mm thick. Thermocouples were used to measure the temperature rise near the crack tip. The effects of specimen size and side-groove on the cryogenic fracture properties of this alloy are examined. Examination of the fracture surface of CT specimens by scanning electron microscopy showed ductile failure by microvoid coalescence. The effect of inclusion on fracture mechanics parameters (JQ, JIC) is also discussed using energy dispersive X-ray analyser.