0000000000117159

AUTHOR

Marco Utili

showing 8 related works from this author

Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System

2021

Abstract The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter a…

Nuclear engineeringCPS; ITER; PbLi loop; TES; WCLL TBS; WCSchemistry.chemical_elementPbLi loopBlanket01 natural sciences010305 fluids & plasmasConceptual designITER0103 physical sciencesWater coolingGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringWater cooledCoolantNuclear Energy and EngineeringchemistryEnvironmental scienceSystems designLithiumCPSWCSTESWCLL TBS
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Integration of DEMO hazard piping into the tokamak building

2021

Abstract Because of the complexity of the design of a Fusion Power Plant like the EU DEMOnstration power plant the study of the plant layout must proceed in parallel with the design of the major systems. This is necessary to ensure that the design of the plant incorporates from the very beginning sound considerations on: • Safety and licensing, • Personnel security in context with operation and maintenance, • Adequate plant availability, and • Safe performance operation including delivery of few hundred MW net electric power to the electrical grid. Though it is a process of trial and change that follows the design evolution, this approach allows a better and continuous control of the numero…

TokamakPower stationComputer sciencebusiness.industryMechanical EngineeringNuclear engineeringMaintainabilityContext (language use)Fusion powerNuclear powerElectrical gridlaw.inventionNuclear Energy and EngineeringlawGeneral Materials ScienceElectric powerbusinessCivil and Structural EngineeringFusion Engineering and Design
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Status of the EU DEMO HCLL breeding blanket design development

2018

International audience; In the framework of the European “HORIZON 2020” innovation and research programme, the EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO). One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. CEA-Saclay, with the support of Wigner-RCP and Centrum výzkumu Řež, is in charge of the development of one of the four BB concepts investigated in Europe for DEMO: the Helium Cooled Lithium Lead (HCLL) BB. The rationales of the HCLL are the use of Eurofer as structural material, eutectic liquid lithium-…

Computer scienceNuclear engineeringBlanketBreeding7. Clean energy01 natural sciences010305 fluids & plasmasTritium breeding ratio0103 physical sciencesGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringBreeding BlanketHelium gasMechanical EngineeringFusion power[INFO.INFO-MO]Computer Science [cs]/Modeling and SimulationCoolantNuclear Energy and EngineeringElectromagnetic shieldingHCLLBlanketMaterials Science (all)Design evolution
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Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project

2019

The water-cooled lithium-lead breeding blanket is in the pre-conceptual design phase. It is a candidate option for European DEMO nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium-lead as breeder-multiplier, pressurized water as coolant and EUROFER as structural material. Current design is based on DEMO 2017 specifications. Two separate water systems are in charge of cooling the first wall and the breeding zone: thermo-dynamic cycle is 295–328 °C at 15.5 MPa. The breeder enters and exits from the breeding zone at 330 °C. Cornerstones of the design are the single module segment approach and the water manifold between the breeding blanket box and the back suppo…

Breeding blanket; DEMO; EUROfusion; WCLLWCLL; breeding blanket; DEMO; EUROfusionComputer scienceNuclear engineeringBlanket01 natural sciences010305 fluids & plasmaslaw.inventionBreeder (animal)Conceptual designlaw0103 physical sciencesGeneral Materials ScienceEUROfusion010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringPressurized water reactorFusion powerCoolantWCLLDesign phaseNuclear Energy and EngineeringMaterials Science (all)Breeding blanketBreeding blanket; DEMO; EUROfusion; WCLL; Civil and Structural Engineering; Nuclear Energy and Engineering; Materials Science (all); Mechanical Engineering
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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

2021

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…

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 construction
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Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

2020

Abstract In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Water Cooled Lithium Lead (WCLL) concepts are being developed as possible candidates to become driver Breeding Blanket (BB) for the EU DEMO, which aims at the tritium self-sufficiency and net electricity production. The two BB design options encompass water or helium as coolants and solid ceramic with beryllium/beryllides or PbLi as tritium breeder and neutron multipliers. The BB segments have evolved towards a more stable conceptual design taking into account multiple feasibility aspects and requirements imposed by interfacing systems. Possible solutions to improve shielding capabiliti…

TokamakTritium extraction and removalNuclear engineeringchemistry.chemical_elementIsolation valveBlanket7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionBreeder (animal)Conceptual designlaw0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringCoolant purificationCoolantElectricity generationNuclear Energy and EngineeringchemistryEnvironmental scienceBreeding blanketBeryllium
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WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

2017

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 norma…

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 systemFusion Engineering and Design
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Progress in EU Breeding Blanket design and integration

2018

Abstract In Europe (EU), in the frame of the EUROfusion consortium activities, four Breeding Blanket (BB) concepts are being developed with the aim of fulfilling the performances required by a near-term fusion power demonstration plant (DEMO) in terms of tritium self-sufficiency and electricity production. The four blanket options cover a wide range of technological possibilities, as water and helium are considered as possible coolants and solid ceramic breeder in combination with beryllium and PbLi as tritium breeder and neutron multipliers. The strategy for the BB selection and operation has to account for the challenging schedule of the EU DEMO, the ambitious operational requirements of …

Computer scienceIn-vessel and ex-vessel componentsBlanketContinuous design7. Clean energy01 natural sciencesBalance of plan010305 fluids & plasmas[SPI]Engineering Sciences [physics]Balance of plant; Breeding Blanket; In-vessel and ex-vessel components; Civil and Structural Engineering; Nuclear Energy and Engineering; Materials Science (all); Mechanical Engineering0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringBalance of plantBreeding BlanketMechanical EngineeringFrame (networking)Schedule (project management)tIn-vessel and ex-vessel componentsElectricity generationNuclear Energy and Engineering13. Climate actionInterfacingSystems engineeringDemonstration PlantIn-vessel and ex-vessel componentMaterials Science (all)Design evolution
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