Torus configuration and materials selection on a fusion DEMO reactor, SlimCS

K. Tobita, S. Nishio, H. Tanigawa, M. Enoeda, T. Isono, H. Nakamura, D. Tsuru, S. Suzuki, T. Hayashi, K. Tsuchiya, T. Hayashi, T. Nishitani

Research output: Contribution to journalArticlepeer-review

23 Citations (Scopus)

Abstract

SlimCS is the conceptual design of a compact fusion DEMO plant assuming technologies foreseeable in 2020-2030s. For continuity of blanket technology from the Japanese ITER-TBM, the prime option of blanket is water-cooled solid breeder with Li2TiO3 (or Li4SiO4) and Be. A reduced-activation ferritic-martensitic steel (RAFM) and subcritical water are chosen as the structural material and coolant, respectively. The reactor has somewhat complex torus configuration with a sector-wide conducting plate slipped in between the replaceable (front) and permanent (back) blanket. In order to allow flexibility of maintenance in such a complex configuration, sector transport hot cell maintenance scheme is adopted. This paper describes characteristics of SlimCS with a focus on materials selection.

Original languageEnglish
Pages (from-to)888-892
Number of pages5
JournalJournal of Nuclear Materials
Volume386-388
Issue numberC
DOIs
Publication statusPublished - 2009 Apr 30
Externally publishedYes

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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