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 language | English |
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Pages (from-to) | 87-95 |
Number of pages | 9 |
Journal | Fusion Engineering and Design |
Volume | 136 |
DOIs | |
State | Published - Nov 2018 |
Externally published | Yes |
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.
Funders | Funder number |
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Euratom research and training programme 2014–2018 | |
Horizon 2020 Framework Programme | |
H2020 Euratom | 633053 |
Keywords
- Breeding blanket
- DEMO
- Design integration
- In-vessel components
- Tokamak