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Thermal-hydraulic scaling of the prototypical mock-up for European DEMO HCPB breeding blanket

Verma, Gaurav 1; Zhou, Guangming 1; Hernández, Francisco A. 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

The Helium-Cooled Pebble Bed (HCPB) blanket concept is a leading candidate for the driver blanket in the European Fusion Demonstration Power Plant (DEMO), developed within the EUROfusion framework's Work Package Breeding Blanket (WPBB). A crucial component of the HCPB blanket is the First Wall (FW), which must withstand high heat fluxes from the plasma while maintaining a uniform temperature distribution as much as possible. This uniformity is achieved through an alternating coolant flow design. The present study focuses on the thermal-hydraulic scaling methodology for the First Wall-Prototype Mock-Up (FW-PMU) to replicate the HCPB blanket's thermal and hydraulic performance. The FW-PMU is designed to emulate the flow distribution and thermal behavior of the HCPB Breeding Blanket (BB) First Wall, including flow patterns from the Breeder Zone Manifold to the fuel-breeder pins. In the present work, a power-to-volume scaling approach is employed to maintain the characteristic time ratio by analyzing non-dimensional parameters, while scaling of component dimensions in the breeder zone manifold ensures a consistent velocity field. ... mehr

Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 05.2025
Sprache Englisch
Identifikator ISSN: 0920-3796
KITopen-ID: 1000180156
Erschienen in Fusion Engineering and Design
Verlag Elsevier
Band 214
Seiten 114924
Nachgewiesen in Dimensions
Scopus
Web of Science
OpenAlex

Verlagsausgabe §
DOI: 10.5445/IR/1000180156
Veröffentlicht am 18.03.2025
Seitenaufrufe: 24
seit 18.03.2025
Downloads: 10
seit 22.03.2025
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