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Search Results: Records 1-7 displayed on this page of 7
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Journal Articles

Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER

Hirose, Takanori; Seki, Yohji; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Tsuru, Daigo; Enoeda, Mikio; Serizawa, Hisashi*; Yamaoka, Hiroto*

Fusion Engineering and Design, 85(7-9), p.1426 - 1429, 2010/12

https://doi.org/10.1016/j.fusengdes.2010.03.066
 Times Cited Count：8 Percentile：49.36(Nuclear Science & Technology)

This paper describes packing experiment of tritium breeder pebbles into a full-scale Tritium-Breeder-Container (TBC) mockup. A full scale mockup of the TBC for Water Cooled Solid Breeder - Test Blanket Module has been successfully developed using a reduced activation ferritic steel, F82H. A full-scale TBC mock-up was successfully fabricated with the fiber laser welding, and its dimensions are 74 $$times$$ 112 $$times$$ 990 mm$$^{3}$$. It was confirmed to be gastight under pressurized helium up to 0.5 MPa. By using the fabricated mockup, packing tests were performed with Li$$_{2}$$TiO$${3}$$ pebbles of 1mm diameter. The pebbles were packed into the TBC through sweep gas lines penetrating the tube plates. X-ray tomography revealed that dense packing was uniformly achieved in the whole TBC.

Journal Articles

Development of optimum manufacturing technologies of radial plates for the ITER toroidal field coils

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Abe, Kanako*; Shimizu, Tatsuya; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*; Takayanagi, Tadatoshi*

Fusion Engineering and Design, 82(5-14), p.1473 - 1480, 2007/10

https://doi.org/10.1016/j.fusengdes.2007.08.013
 Times Cited Count：7 Percentile：47.2(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Manufacturing study and trial fabrication of radial plate for ITER toroidal field coil

Abe, Kanako*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*

IEEE Transactions on Applied Superconductivity, 16(2), p.807 - 810, 2006/06

https://doi.org/10.1109/TASC.2006.873261
 Times Cited Count：12 Percentile：51.46(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development of laser cutting/welding system for remote maintenance of ITER manifold

Yamaoka, Hiroto*; Tsuchiya, Kazuyuki*; Awano, Toshihiko*; Oka, Kiyoshi

Ishikawajima Harima Giho, 42(5), p.260 - 264, 2002/09

http://ci.nii.ac.jp/naid/40005409717

no abstracts in English

Oral presentation

Welding deformation and mechanical proprieties of 316LN welded joint for ITER superconducting coil

Nakajima, Hideo; Hamada, Kazuya; Takano, Katsutoshi; Tsutsumi, Fumiaki; Kawano, Katsumi; Okuno, Kiyoshi; Yamaoka, Hiroto*; Kakui, Hideo*; Nakamura, Taizo*; Morinaga, Yasuhito*

no journal, , 

no abstracts in English

Oral presentation

Development of manufacturing technology of radial plate for ITER TF coil

Nakajima, Hideo; Hamada, Kazuya; Takano, Katsutoshi; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Nakamura, Taizo*; Yamana, Norihiko*

no journal, , 

no abstracts in English

Oral presentation

Development of welding procedure for ITER-TF coil structure

Niimi, Kenichiro; Nakajima, Hideo; Hamada, Kazuya; Takano, Katsutoshi; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Chida, Yutaka*; Seto, Masaru*; Soejima, Koji*; et al.

no journal, , 

no abstracts in English

7 (Records 1-7 displayed on this page)
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