Further improvements of the water-cooled Pb-17Li blanket

M.A. Fütterer, G. Benamati, I. Ricapito, L. Giancarli, G. Le Marois, A. Li Puma, Y. Poitevin, J. Reimann, J.-F. Salavy, J. Szczepanski, G. Vella, G. Ruvutuso

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The water-cooled lithium-lead (WCLL) blanket is based on reduced-activation ferritic-martensitic steel as the structural material, the liquid alloy Pb-17Li as breeder and neutron multiplier, and water at typical PWR conditions as coolant. It was developed for DEMO specifications and shall be tested in ITER. In 1999, a reactor parameter optimization was performed in the EU which yielded improved specifications of what could be an attractive fusion power plant. Compared to DEMO, such a power reactor would be different in lay-out, size and performance, thus requiring to better exploit the potential of the WCLL blanket concept in conjunction with a water-cooled divertor. Several new approaches are currently under evaluation. This paper outlines several specific modifications, it highlights progress made on various issues and outlines the R&D work which is still required to define an improved reference design for the WCLL concept. © 2001 Elsevier Science B.V. All rights reserved.
Original languageEnglish
Pages (from-to)523 - 527
Number of pages5
JournalFusion Engineering and Design
Publication statusPublished - Nov 2001
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering

Cite this

Fütterer, M. A., Benamati, G., Ricapito, I., Giancarli, L., Le Marois, G., Li Puma, A., ... Ruvutuso, G. (2001). Further improvements of the water-cooled Pb-17Li blanket. Fusion Engineering and Design, 58-59, 523 - 527. https://doi.org/10.1016/S0920-3796(01)00489-6