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Exploratory thermo-mechanical assessment of a pin of the Helium Cooled Pebble Bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor

Gioè, A. ; Hernández, F. A. 1; Bongiovì, G.; Catanzaro, I.; Quartararo, A.; Vallone, E.; Agnello, G.; Spagnuolo, G. A. 1; d’Amico, S.; Chiovaro, P.; Di Maio, P. A.
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

The Helium-Cooled Pebble-Bed (HCPB) Breeding Blanket (BB) concept is one of the two candidates for the driver blanket of the EU-DEMO nuclear fusion reactor. It shall adopt gaseous helium at 8.0 MPa as coolant and tritium carrier together with solid tritium breeder and neutron multiplier. With the aim of overcoming the critical issues that emerged during the DEMO pre-conceptual design phase, potential HCPB BB design variants are under development in the frame of the DEMO R&D. Among them, the concept envisaging a modular pin monoblock presents the advantages of having all the functional materials contained in a pin structure and of avoiding the need for a first wall, remarkably easing manufacturing. Hence, in this work, a campaign of thermo-mechanical scoping analyses aimed at assessing the performances of this novel BB concept is presented. Starting from a previous thermofluid-dynamic assessment presented in another work, different geometric layouts have been assessed in view of the rules prescribed by the RCC-MRx structural design code. In particular, a multi-scale analysis has been carried out assessing, in a first phase, the global thermo-mechanical performances of the equatorial region of the Central Outboard Blanket segment moving, in a second phase, to the detailed structural analysis of the pin internals. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000187890
Veröffentlicht am 02.12.2025
Originalveröffentlichung
DOI: 10.1016/j.fusengdes.2025.115314
Scopus
Zitationen: 1
Web of Science
Zitationen: 1
Dimensions
Zitationen: 1
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 11.2025
Sprache Englisch
Identifikator ISSN: 0920-3796
KITopen-ID: 1000187890
HGF-Programm 31.13.04 (POF IV, LK 01) In Vessel Components
Erschienen in Fusion Engineering and Design
Verlag Elsevier
Band 220
Seiten Art.-Nr. 115314
Vorab online veröffentlicht am 10.07.2025
Nachgewiesen in Web of Science
OpenAlex
Dimensions
Scopus
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