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RESEARCH PRODUCT
Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor
Fabio MoroPietro Alessandro Di MaioRuggero ForteAndrea TaralloG. MarianoRosaria VillariAlessandro Del NevoRocco MozzilloG. BongiovìFabio GiannettiAlessandro TassoneEmanuela MartelliGiuseppe Di GironimoGianfranco CarusoMarica EboliNicola ForgioneP. Arenasubject
liquid metal technologyNuclear and High Energy PhysicsLiquid metalPower stationLayoutComputer scienceNuclear engineeringNeutronBlanket01 natural sciences7. Clean energy010305 fluids & plasmasBreeding blanket (BB); Demonstration Power Plant (DEMO); fusion reactor design; liquid metal technology; Nuclear and High Energy Physics; Condensed Matter PhysicsBreeding blanket (BB)Conceptual design0103 physical sciencesliquid metal technology.Nuclear fusion010306 general physicsSettore ING-IND/19 - Impianti NucleariNuclear and High Energy PhysicMetalDemonstration Power Plant (DEMO)Fusion powerCondensed Matter PhysicsManifoldbreeding blanket; DEMO; fusion reactor design; liquid metal technologyCoolantElectricity generationCoolantPower generationfusion reactor designdescription
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for the implementation in the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa as the coolant, and EUROFER as the structural material. The current design is based on the single module segment approach and follows the requirements of the DEMO-2015 baseline design. The module is constituted by a basic toroidal-radial cell that is recursively repeated along the poloidal direction where the liquid metal flows along a radial-poloidal path. The heat generated by the fusion reactions is extracted by means of separate cooling systems for the breeding zone and the first wall. A back supporting structure is dedicated to withstand loads of the module during normal and off-normal operations. Water and PbLi manifolds are integrated with primary heat transport and tritium extraction systems. The status of the conceptual design is presented, critically discussing its rationale and main features as supported by neutronic, thermal-hydraulic, magneto-hydrodynamic, and thermo-mechanic analyses. Recent results are outlined, pointing out open issues and development needs.
| year | journal | country | edition | language |
|---|---|---|---|---|
| 2018-05-01 | IEEE Transactions on Plasma Science |