Conceptual design activities and key issues on LHD-type reactor FFHR

An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement a...

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Published in:Fusion engineering and design Vol. 81; no. 23; pp. 2703 - 2712
Main Authors: Sagara, A., Mitarai, O., Imagawa, S., Morisaki, T., Tanaka, T., Mizuguchi, N., Dolan, T., Miyazawa, J., Takahata, K., Chikaraishi, H., Yamada, S., Seo, K., Sakamoto, R., Masuzaki, S., Muroga, T., Yamada, H., Fukada, S., Hashizume, H., Yamazaki, K., Mito, T., Kaneko, O., Mutoh, T., Ohyabu, N., Noda, N., Komori, A., Sudo, S., Motojima, O.
Format: Journal Article Conference Proceeding
Language:English
Published: Amsterdam Elsevier B.V 01-11-2006
New York, NY Elsevier Science
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Summary:An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm 2 and a neutron wall loading around 1.5 MW/m 2. R&D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets.
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ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2006.07.057