Overview over DEMO design integration challenges and their impact on component design concepts

C. Bachmann, S. Ciattaglia, F. Cismondi, T. Eade, G. Federici, U. Fischer, T. Franke, C. Gliss, F. Hernandez, J. Keep, M. Loughlin, F. Maviglia, F. Moro, J. Morris, P. Pereslavtsev, N. Taylor, Z. Vizvary, R. Wenninger

Research output: Contribution to journalArticlepeer-review

84 Scopus citations

Abstract

The EU fusion roadmap defines as one of its goals the development of a Demonstration Fusion Power Reactor (DEMO) to follow ITER. This device shall be tritium self-sufficient, produce net electricity, and acts as a component test facility to demonstrate fusion power plant relevant technologies, e.g. those of the breeding blanket. This article identifies the main DEMO requirements, introduces the rationales for the selected architecture of the DEMO tokamak, and describes how the configuration of the main tokamak components has been derived. This includes (i) the DEMO shielding concept, (ii) the segmentation of the in-vessel components and their maintenance strategy, (iii) an overview of the vessel and in-vessel component technologies, and (iv) a description of the integrated design of the breeding blanket.

Original languageEnglish
Pages (from-to)87-95
Number of pages9
JournalFusion Engineering and Design
Volume136
DOIs
StatePublished - Nov 2018
Externally publishedYes

Funding

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014?2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

FundersFunder number
Euratom research and training programme 2014–2018
Horizon 2020 Framework Programme
H2020 Euratom633053

    Keywords

    • Breeding blanket
    • DEMO
    • Design integration
    • In-vessel components
    • Tokamak

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