Design and development of the Flibe blanket for helical-type fusion reactor FFHR

A. Sagara, H. Yamanishi, S. Imagawa, T. Muroga, T. Uda, T. Noda, S. Takahashi, K. Fukumoto, T. Yamamoto, H. Matsui, A. Kohyama, H. Hasizume, S. Toda, A. Shimizu, A. Suzuki, Y. Hosoya, S. Tanaka, T. Terai, Dai Kai Sze, O. Motojima

Research output: Contribution to journalArticlepeer-review

56 Citations (Scopus)

Abstract

Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyzes using the MCNP-4B code, on thermal and stress analyzes using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented.

Original languageEnglish
Pages (from-to)661-666
Number of pages6
JournalFusion Engineering and Design
Volume49-50
DOIs
Publication statusPublished - 2000 Nov

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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