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Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

Palermo, Iole ; Hernandez, Francisco A. 1; D’Amico, Salvatore; Park, Jin Hun 1; Pereslavtsev, Pavel 1; Zhou, Guangming 2; Zumalde, Iñaki
1 Karlsruher Institut für Technologie (KIT)
2 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts: Water-Cooled Lithium Lead (WCLL) and Helium-Cooled Pebble Bed (HCPB). The WLCB design represents an alternative hybrid approach, combining advantageous features of both WCLL and HCPB to mitigate their respective limitations: (1) shielding inefficiencies, challenging neutron multiplier technology, and integration concerns in HCPB; (2) challenges with tritium extraction from PbLi in WCLL variants; and (3) the reliance on anti-permeation barriers. In lieu of beryllium, alternative neutron multipliers—particularly lead—have been explored.
This work focuses on the neutronic optimization of the WLCB concept, with an emphasis on tritium breeding performance. Extensive neutronic simulation campaigns were conducted to optimize key design parameters, including toroidal and radial blanket layouts, cooling plate dimensions and water content, neutron multiplier zoning and materials (Pb, Be12Ti, Zr5Pb3, C, ZrH2), 6Li enrichment, ceramic breeder material, ceramic packing factor, and First Wall (FW) design to achieve the best results in terms of Tritium Breeding Ratio (TBR).
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Verlagsausgabe §
DOI: 10.5445/IR/1000188285
Veröffentlicht am 09.12.2025
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 12.2025
Sprache Englisch
Identifikator ISSN: 2352-1791
KITopen-ID: 1000188285
HGF-Programm 31.13.04 (POF IV, LK 01) In Vessel Components
Erschienen in Nuclear Materials and Energy
Verlag Elsevier
Band 45
Seiten 102022
Nachgewiesen in OpenAlex
Dimensions
Web of Science
Scopus
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