Recently, an integrated program of conceptual design activities for the European DEMO reactor was launched in the framework of the EUROfusion Consortium, where reliable power handling capability was identified as one of the most critical scientific as well as technological challenges for a DEMO reactor. The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. The DEMO divertor target will have to withstand extreme thermal loads where the local peak heat flux is expected to reach up to 20 MW/m2during slow transient events in DEMO. To assure sufficient heat removal capability of the divertor target against normal and transient operational scenarios under expected cumulative neutron dose of up to 13 dpa is one of the fundamental engineering challenges imposed on target design. To develop the design of the DEMO divertor and related technologies, an R&D work package ‘Divertor’ has been set up in this consortium. The subproject ‘Target Development’ is devoted to the development of the conceptual design and the core technologies of the plasma-facing target. Devising and implementing novel structural heat sink materials (e.g. W/Cu composites) to advanced target design concepts is one of the major objectives of this subproject. In this paper, the underlying design requirements imposed by the envisaged power exhaust goal and the prominent material-design interface issues are discussed. In addition, the candidate design concepts being currently considered are presented together with the related material issues. Finally, the first results achieved so far are presented.
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science (miscellaneous)
- Nuclear Energy and Engineering
You, J. H., Visca, E., Bachmann, C., Barrett, T., Crescenzi, F., Fursdon, M., Greuner, H., Guilhem, D., Languille, P., Li, M., McIntosh, S., Müller, A. V., Reiser, J., Richou, M., & Rieth, M. (2016). European DEMO divertor target: Operational requirements and material-design interface. Nuclear Materials and Energy, 9, 171 - 176. https://doi.org/10.1016/j.nme.2016.02.005