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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.; Di Maio, P. A.; Di Mambro, G.; Domptail, F.; ... mehr

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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Verlagsausgabe §
DOI: 10.5445/IR/1000142224
Veröffentlicht am 24.01.2022
Originalveröffentlichung
DOI: 10.1016/j.fusengdes.2022.113010
Scopus
Zitationen: 49
Dimensions
Zitationen: 52
Cover der Publikation
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 Web of Science
Dimensions
Scopus
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