Search results for "Breeding blanket"

showing 10 items of 43 documents

Identification of blanket design points using an integrated multi-physics approach

2017

Abstract The breeding blanket (BB) is one of the key components for a fusion reactor. It is expected to sustain and remove considerable heat loads due to the heat flux coming from the plasma and the nuclear power deposited by the fusion neutrons. In the design of the BB, the engineering requirements of nuclear, material and safety kind are involved. In the European DEMO project, several efforts are dedicated to the development of an integrated simulation-design tool able to perform a multi-physics analysis, allowing the characterisation of BB design points which are consistent from the neutronic, thermal-hydraulic and thermo-mechanical point of view. Furthermore, at Karlsruhe Institute of T…

TechnologyNuclear engineeringDEMO reactorBlanket7. Clean energy01 natural sciences010305 fluids & plasmasCoupling0103 physical sciencesMulti-physics approachGeneral Materials SciencePoint (geometry)Design point010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringCouplingRequirements engineeringbusiness.industryMechanical EngineeringNuclear powerFusion powerFinite element methodNuclear Energy and EngineeringHeat fluxBreeding blanketbusinessddc:600Fusion Engineering and Design
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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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The DEMO water-cooled lead–lithium breeding blanket: design status at the end of the pre-conceptual design phase

2021

The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on the design were considered at the same time. This new approach allowed for the design team to create a WCLL BB layout that is able to comply with different foreseen requirements in terms of integration, tritium self-sufficiency, and TH and TM needs. In this paper, the rationale behind the design choices and the main characteristics of the WCLL BB needed for the EU-DEMO …

TechnologyQH301-705.5QC1-99901 natural sciences010305 fluids & plasmas0103 physical sciencesGeneral Materials ScienceBiology (General)010306 general physicsInstrumentationQD1-999DEMOSettore ING-IND/19 - Impianti Nuclearinuclear fusionFluid Flow and Transfer Processesbreeding blanketProcess Chemistry and TechnologyTPhysicsGeneral EngineeringDEMO; nuclear fusion; breeding blanket; nuclear reactorEngineering (General). Civil engineering (General)Computer Science ApplicationsChemistrynuclear reactorTA1-2040
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Structural assessment of a whole toroidal sector of the HELIAS 5-B breeding blanket

2021

Abstract The European roadmap for the realization of fusion energy considers the stellarator line as a possible long-term alternative to a tokamak DEMO. In this context, from the plasma physics standpoint, the most promising option is a five-field period power plant called HELIcal-axis Advanced Stellarator (HELIAS) 5-B. In order to allow the electricity production, the HELIAS 5-B reactor must be endowed with a breeding blanket (BB). Hence, in this paper, the advancements in the HELIAS 5-B BB design are reported. In particular, the structural assessment of a whole BB period, extending along toroidal direction for 72 °, is depicted. A geometric configuration encompassing dummy BB segments has…

TechnologyTokamakHeliasNuclear engineeringFEM analysisContext (language use)Blanket01 natural sciences010305 fluids & plasmaslaw.inventionThermomechanicsHELIASlaw0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMathematicsStellaratorToroidbiologyMechanical EngineeringFusion powerbiology.organism_classificationFinite element methodNuclear Energy and EngineeringBreeding blanketddc:600StellaratorFusion Engineering and Design
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Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket

2019

The wide range of requirements and constraints involved in the design of nuclear components for fusion reactors makes the development of multi-physics analysis procedures of utmost importance. In the framework of the European DEMO project, the Karlsruhe Institute of Technology (KIT) is dedicating several efforts to the development of a multi-physics analysis tool allowing the characterization of breeding blanket design points which are consistent from the neutronic, thermal-hydraulic and thermal-mechanical points of view. In particular, a procedure developed at KIT is characterized by the implementation of analysis software only. A preliminary step for the validation of such a procedure ha…

Technologybreeding blanketHCPBDEMO reactorBlanketFusion power7. Clean energy01 natural sciences010305 fluids & plasmasComputational Mathematics0103 physical sciencesComputer Science (miscellaneous)Systems engineeringdesign pointmulti-physicscoupling010306 general physicsddc:600Settore ING-IND/19 - Impianti Nucleari
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Preliminary thermal optimization and investigation of the overall structural behaviour of the EU-DEMO water-cooled lead lithium left outboard blanket…

2022

The conceptual design phase of the EU-DEMO reactor has been recently launched, with the aim of evolving the DEMO pre-conceptual layout towards a more robust and articulated geometric configuration able to cope with most of the design requirements and to show further margins for the passing of the current potential show-stoppers. Hence, the achievement of the conceptual design of the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB) is one of the milestones the EUROfusion consortium aims to achieve in the close future. To this purpose, within the framework of the research activities promoted by EUROfusion, a research campaign has been launched at the University of Palermo, in close cooper…

ThermomechanicsLateral outboardNuclear Energy and EngineeringMechanical EngineeringDWTs optimizationFEM analysisGeneral Materials ScienceBreeding blanketSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringWCLL
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Development of helium coolant DEMO first wall model for SYCOMORE system code based on HCLL concept

2018

Abstract The conceptual design of the demonstration fusion power reactor, known as DEMO, is ongoing and several reactor configurations have to be investigated by exploring different design parameters. For these reasons, within the European framework, systems codes like SYCOMORE (SYstem COde for MOdelling tokamak REactor) have been developed. SYCOMORE includes several specific modules, one of which is aimed to define a suitable design of the helium breeding blanket. The research activity has been devoted to improve the method to define automatically the First Wall design starting from thermal-hydraulic and thermo-mechanical considerations, using analytical design formulae and, also, taking i…

TokamakComputer scienceNuclear engineeringBlanket7. Clean energy01 natural sciences010305 fluids & plasmaslaw.invention[SPI]Engineering Sciences [physics]Development (topology)Conceptual designlawSystem code0103 physical sciencesThermalGeneral Materials Science010306 general physicsDEMOCivil and Structural EngineeringFW HCLLMechanical EngineeringFusion powerFinite element methodNuclear Energy and EngineeringBreeding blanketGeometric modelingSYCOMORE
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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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Advancements in DEMO WCLL breeding blanket design and integration

2018

The water-cooled lithium-lead breeding blanket is a candidate option for the European Demonstration Power Plant (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. The current design is based on DEMO 2015 specifications and represents the follow-up of the design developed in 2015. The single-module-segment approach is employed. This is constituted by a basic geometry repeated along the poloidal direction. The power is removed by means of radial-toroidal (i.e., horizontal) water cooling tubes in the breeding zone. The lithium-lead flows in a radial-poloidal dire…

breeding blanketbreeding blanket DEMO WCLLbreeding blanket; DEMO; WCLLDEMOSettore ING-IND/19 - Impianti NucleariWCLL
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Development and application of multiscale procedures for the thermomechanical analysis of the DEMO Water-Cooled Lithium Lead Breeding Blanket

2022

The Breeding Blanket is an essential component of the DEMO fusion reactor and its design is one of the pivotal purposes of the DEMO project. Indeed, this component has to withstand severe operating conditions, as it is directly exposed to the plasma, making its design particularly challenging. In particular, the Water-Cooled Lithium-Lead (WCLL) BB concept is one of the candidates currently considered for the conceptual design of the European DEMO reactor. The development of a robust BB system is crucial for the design of the whole DEMO reactor and the thermo-mechanical assessment of the whole BB segments is mandatory to allow checking their structural performances in different loading scena…

breeding blankets thermo-mechanics analysis procedureFEM analysisSettore ING-IND/19 - Impianti NucleariWCLL
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