Divertor of the European DEMO: Engineering and technologies for power exhaust
You, J. H.; Mazzone, G.; Visca, E.; Greuner, H.; Fursdon, M.; Addab, Y.; Bachmann, C.; Barrett, T.; Bonavolontà, U.; Böswirth, B.; Castrovinci, F. M.; Carelli, C.; Coccorese, D.; Coppola, R.; Crescenzi, F.; Di Gironimo, G.; Maio, P. A. Di; Di Mambro, G.; Domptail, F.; ... mehrDongiovanni, D.; Dose, G.; Flammini, D.; Forest, L.; Frosi, P.; Gallay, F.; Ghidersa, B. E.; Harrington, C.; Hunger, K.; Imbriani, V.; Li, M.; Lukenskas, A.; Maffucci, A.; Mantel, N.; Marzullo, D.; Minniti, T.; Müller, A. V.; Noce, S.; Porfiri, M. T.; Quartararo, A.; Richou, M.; Roccella, S.; Terentyev, D.; Tincani, A.; Vallone, E.; Ventre, S.; Villari, R.; Villone, F.; Vorpahl, C.; Zhang, K.
Abstract:
In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reaction and external heating must be exhausted through the narrow area of the divertor targets. The targets must withstand the intense bombardment of the diverted particles where high heat fluxes are generated and erosion takes place on the surface. A considerable amount of volumetric nuclear heating power must also be exhausted. To cope with such an unprecedented power exhaust challenge, a highly efficient cooling capacity is required. Furthermore, the divertor must fulfill other critical functions such as nuclear shielding and channeling (and compression) of exhaust gas for pumping. Assuring the structural integrity of the neutron-irradiated (thus embrittled) components is a crucial prerequisite for a reliable operation over the lifetime. Safety, maintainability, availability, waste and costs are another points of consideration.
In late 2020, the Pre-Conceptual Design activities to develop the divertor of the European demonstration fusion reactor were officially concluded. On this occasion, the baseline design and the key technology options were identified and verified by the project team (EUROfusion Work Package Divertor) based on seven years of R&D efforts and endorsed by Gate Review Panel.
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In this paper, an overview of the load specifications, brief descriptions of the design and the highlights of the technology R&D work are presented together with the further work still needed.
Zugehörige Institution(en) am KIT |
Institut für Neutronenphysik und Reaktortechnik (INR) |
Publikationstyp |
Zeitschriftenaufsatz |
Publikationsmonat/-jahr |
02.2022 |
Sprache |
Englisch |
Identifikator |
ISSN: 0920-3796
KITopen-ID: 1000142224 |
HGF-Programm |
31.13.04 (POF IV, LK 01) In Vessel Components |
Erschienen in |
Fusion engineering and design |
Verlag |
Elsevier |
Band |
175 |
Seiten |
Art.-Nr.: 113010 |
Nachgewiesen in |
Scopus Web of Science Dimensions
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Globale Ziele für nachhaltige Entwicklung |
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