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Journal Articles

Design progress of the ITER in-wall shielding

Morimoto, Masaaki; Ioki, Kimihiro; Terasawa, Atsumi; Utin, Y.*

Fusion Science and Technology, 52(4), p.834 - 838, 2007/11

 Times Cited Count:1 Percentile:11.35(Nuclear Science & Technology)

The ITER in-wall shielding is mounted in between the double walls of the Vacuum Vessel. Boron-doped stainless steel and SS430 ferritic steel are used. The design improvement of the in-wall shielding has focused on reducing electromagnetic forces acting on shielding blocks. It has been found that the calculated electromagnetic forces have been significantly reduced. Magnetization forces have also been calculated for ferromagnetic inserts. Based on these load conditions, structural analyses have been performed and structural integrity has been validated. Shapes of boron-doped shielding plates which have low ductility are carefully designed to prevent excessive stress concentrations and not to take high mechanical loads. This makes shielding plate design simpler and more robust. Suitable dimensions and gaps between shielding blocks and between shielding block and the VV have been designed to fit to tolerances of the VV.

Journal Articles

ITER limiters moveable during plasma discharge and optimization of ferromagnetic inserts to minimize toroidal field ripple

Ioki, Kimihiro; Chuyanov, V.*; Elio, F.*; Garkusha, D.*; Gribov, Y.*; Lamzin, E.*; Morimoto, Masaaki; Shimada, Michiya; Sugihara, Masayoshi; Terasawa, Atsumi; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

Two important design updates have been made in the ITER VV and in-vessel components recently. One is the introduction of limiters moveable during a plasma discharge, and the other is optimization of the ferromagnetic insert configuration to minimize the toroidal field ripple. In the new limiter concept, the limiters are retracted by 8 cm during the plasma flat top phase in the divertor configuration. This concept gives important advantages: (1) the particle and heat loads due to disruptions, ELMs and blobs on the limiters will be mitigated approximately by a factor 1.5 or more; (2) the gap between the plasma and the ICRH antenna can be reduced to improve the coupling of the ICRH power. The ferromagnetic inserts have previously not been planned to be installed in the outboard midplane region between equatorial ports due to irregularity of tangential ports for NB injection. The result is a relatively large ripple (1 %) in a limited region of the plasma, which nevertheless seems acceptable from the plasma performance viewpoint. However, toroidal field flux lines fluctuate 10 mm due to the large ripple in the FW region. To avoid problems due to the large TF flux line fluctuation, additional ferromagnetic inserts are now planned to be installed in the equatorial port region.

Journal Articles

Development of a 13T-46kA Nb$$_{3}$$Sn conductor and central solenoid model coils for ITER

Takahashi, Yoshikazu; Ando, Toshinari; Hiyama, Tadao; Nakajima, Hideo; Kato, Takashi; Sugimoto, Makoto; Isono, Takaaki; Oshikiri, Masayuki*; Kawano, Katsumi; Koizumi, Norikiyo; et al.

Fusion Engineering and Design, 41(1-4), p.271 - 275, 1998/09

 Times Cited Count:4 Percentile:38.7(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Void fraction effects on stability in cable-in-conduit conductor for varying field due to plasma disruption

Terasawa, Atsumi; Miura, Yushi; Ando, Toshinari; Nozawa, Masanobu*; Isono, Takaaki; Takaya, Yoshiyuki*; Tsuji, Hiroshi; Shimamoto, Susumi

ICEC16/ICMC Proceedings, p.1265 - 1268, 1996/00

no abstracts in English

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