6533b85cfe1ef96bd12bd3fd
RESEARCH PRODUCT
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design
A. Del NevoSalvatore D’amicoPierluigi ChiovaroLorenzo Virgilio BoccacciniF.r. UrgorriMaria Teresa PorfiriAntonio FroioAlessia SantucciFabio CismondiSergio CiattagliaIon CristescuSilvano TostiA. Li PumaR. ArredondoMichael RiethC. GlissRobert StieglitzP.a. Di MaioMatteo D’onorioDavid RapisardaG. FedericiCarlos Hugo MorenoM. ColemanF. FranzaE. ValloneCh. DayJ.c. SchwenzerMarco UtiliI. MoscatoPavel PereslavtsevFrancisco A. HernándezGandolfo Alessandro Spagnuolosubject
TechnologyNuclear engineeringintegration issuesBreeding blanket; Integration issues; Water activation; Tritium management; VVPSSchemistry.chemical_elementIsolation valveSystem safetyBlanketTritium01 natural sciences010305 fluids & plasmasVVPSS0103 physical sciencesFusion reactors -- Design and constructionGeneral Materials Science010306 general physicswater activationSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringIntegrated designbreeding blanket; integration issues; tritium management; VVPSS; water activationbreeding blanketMechanical EngineeringWater -- Thermal propertiesCoolanttritium managementNuclear Energy and EngineeringchemistryHeat transferEnvironmental scienceHelium -- Thermal propertiesPlant designddc:600Power-plants -- Design and constructiondescription
Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates for the integration in the reactor. They are the Water Cooled Lithium Lead and the Helium Cooled Pebble Bed BB concepts. The two BB variants together with the associated ancillary systems drive the design of the overall plant. Therefore, a holistic investigation of integration issues derived by the BB and the installation of its ancillary systems has been performed. The issues related to the water activation due to the 16N and 17N isotopes and the impact on the primary heat transfer systems have been investigated providing guidelines and dedicated solution for the integration of safety devices as isolation valves. The tritium retention and the permeation rates through the blanket and its ancillary systems have been also assessed taking into account different operating points both for the BB and ancillaries and comparing, when possible, the releases with the operating and safety limits. Moreover, the issues related to the tritium start-up inventory as well as the uncertainties on the Tritium Breeding Ratio (TBR) due to the integration of the auxiliary systems within the Vacuum Vessel have been also studied. Finally, the impact of the BB concepts on the safety systems like the Vacuum Vessel Pressure Suppression System is described with a particular focus on the different measures that should be implemented according to the considered concept. All these aspects are then taken into account to drive future developments during the Concept Design Phase.
year | journal | country | edition | language |
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2021-12-01 |