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RESEARCH PRODUCT
Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant
Yves PoitevinGiuseppe VellaA. Li PumaL BarleonJ.-f. SalavyL. GiancarliO.v OgorodnikovaM.a FüttererJ. Szczepanskisubject
Mechanical EngineeringNuclear engineeringDivertorFusion powerBlanketNuclear reactorCoolantlaw.inventionNuclear Energy and EngineeringlawWater coolingEnvironmental scienceGeneral Materials ScienceCost of electricity by sourceCivil and Structural EngineeringPower densitydescription
Abstract Blankets and divertors are key components of a fusion power plant. They have a large impact on the overall plant design, its performance and availability, and on the cost of electricity. The water-cooled Pb–17Li (WCLL) blanket uses reduced activation ferritic–martensitic steel as structural material. It was previously validated under numerous aspects such as TBR, mechanical and thermo-mechanical stability, thermal–hydraulics, MHD, safety and others. This was done assuming the specifications for a European DEMOnstration reactor which were fixed back in 1989. A WCLL blanket would best be combined with a water-cooled divertor so that a single coolant could be used for the entire reactor. Several divertor designs were proposed recently. This paper investigates the applicability of the WCLL blanket concept and a water-cooled divertor in attractive power reactors with increased power densities compared with DEMO.
| year | journal | country | edition | language |
|---|---|---|---|---|
| 2000-11-01 | Fusion Engineering and Design |