6533b85efe1ef96bd12c06d2

RESEARCH PRODUCT

WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Andrea TaralloPietro AgostiniA. Del NevoMarco UtiliG. MarianoEmanuela MartelliRocco MozzilloRosaria VillariFabio MoroG. Di GironimoFabio GiannettiGianfranco CarusoP. ArenaG. BongiovìR. GiammussoMariano TarantinoP.a. Di MaioAlessandro TassoneD. RozziaMarica EboliA. Giovinazzi

subject

Neutron transportComputer scienceBlanket7. Clean energy01 natural sciencesbreeding blanket; CFD; DEMO; WCLL010305 fluids & plasmaslaw.inventionlaw0103 physical sciencesDesign choiceGeneral Materials Science010306 general physicsWCLL Breeding blanket DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL Breeding blanket DEMObusiness.industryMechanical EngineeringLead systemPressurized water reactorFusion powerModular designNuclear Energy and EngineeringSystems engineeringbusinessTransport system

description

Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling tubes in the breeding zone, and on lithium lead flowing in radial-poloidal direction. This design choice is driven by the rationale to have a modular design, where a basic geometry is repeated along the poloidal direction. The modules are connected with a back supporting structure, designed to withstand thermal and mechanical loads due to normal operation and selected postulated accidents. Water and lithium lead manifolds are designed and integrated with a consistent primary heat transport system, based on a reliable pressurized water reactor operating experience, and the lithium lead system. Rationale and features of current status of water-cooled lithium-lead breeding blanket design are discussed and supported by thermo-mechanics, thermo-hydraulics and neutronics analyses. Open issues and areas of research and development needs are finally pointed out.

https://doi.org/10.1016/j.fusengdes.2017.03.020