Search results for "CLL"

showing 10 items of 73 documents

Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket

2017

Abstract Within the framework of EUROfusion R&D activities an intense research campaign has been carried out at the University of Palermo, in close cooperation with ENEA Brasimone, in order to investigate the thermo-mechanical performances of the outboard segment Back-Supporting Structure (BSS) of the DEMO Water-Cooled Lithium Lead breeding blanket (WCLL). In particular, the configuration of the outboard segment BSS, purposely set-up by the WCLL project team during 2015 according to the blanket “multi-module system” concept, has been taken into account in order to study its steady state thermo-mechanical behaviour, paying attention to the simulation of both modules-BSS and BSS-vacuum vessel…

Structure (mathematical logic)business.industryComputer scienceMechanical EngineeringDEMO reactor WCLL blanket BSSDEMO reactorStructural engineeringBlanket01 natural sciencesProject teamFinite element method010305 fluids & plasmasWCLL blanketGeometric designNuclear Energy and EngineeringLinearization0103 physical sciencesSafety criteriaGeneral Materials Science010306 general physicsbusinessBSSSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Maturation of critical technologies for the DEMO balance of plant systems

2022

The Pre-Concept Design (PCD) of the Balance of Plant (BoP) systems of the EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely the Water Cooled Lithium Lead (WCLL) BB and the Helium Cooled Pebble Bed (HCPB) BB. Moreover, the results of a preliminary evaluation of a number of BoP variants are discussed. This paper outlines the steps of the BoP design development, highlighting the project objectives and the strategy for their achievement under the very challenging requirements which include, among others, the intermittent nature of the DEMO plasma heat source. The main achievements during the PCD Phase will be reported together with t…

TechnologyBalance of plantElectric power distributionMechanical EngineeringHCPB BBSteam generatorPower conversion systemPower plants -- Design and constructionNuclear Energy and EngineeringSteam-boilersGeneral Materials SciencePower-plants -- Europebalance of plant; DEMO; HCPB BB; power conversion system; steam generator; WCLL BBddc:600DEMOWCLL BBSettore ING-IND/19 - Impianti NucleariDEMO; Balance of plant; WCLL BB; HCPB BB; Steam generator; Power conversion systemCivil and Structural Engineering
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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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Water Cooled First Wall optimization for WCLL DEMO reactor

2013

WCLL blanketDEMOSettore ING-IND/19 - Impianti NucleariFW
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Optimization of the first wall for the DEMO water cooled lithium lead blanket

2015

The maximum heat load capacity of a DEMO First Wall (FW) of reasonable cost may impact the decision of the implementation of limiters in DEMO. An estimate of the engineering limit of the FW heat load capacity is an essential input for this decision. This paper describes the work performed to optimize the FW of the Water Cooled Lithium-Lead (WCLL) blanket concept for DEMO fusion reactor in order to increase its maximum heat load capacity. The optimization is based on the use of water at typical Pressurised Water Reactors conditions as coolant. The present WCLL FW with a waved plasma-faced surface and with circular channels was studied and the heat load limit has been predicted with FEM analy…

Work (thermodynamics)DesignMaterials scienceMechanical EngineeringNuclear engineeringDesign;DEMO;Blanket;WCLL;First WallFusion powerBlanketFinite element methodWCLLCoolantDesign for manufacturability[SPI]Engineering Sciences [physics]First WallDEMO Blanket WCLL Design First WallNuclear Energy and EngineeringThermalLimiterBlanketGeneral Materials ScienceDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response

2019

Abstract In the framework of EUROfusion Work Package International Cooperation R&D activities, a close collaboration has been started among University of Palermo, ENEA Brasimone and ENEA Frascati for the development of the Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) concept. In this context, a research campaign has been carried out at the University of Palermo in order to investigate the influence of First Wall (FW) cooling water configuration on the nuclear response of the WCLL BB under irradiation in EU-DEMO, in order to gain useful indications for the WCLL BB pre-conceptual designs. To this end, three-dimensional nuclear analyses have been performed by MCNP5 v. 1.6 Monte Carlo…

Work packageNuclear engineeringNeutronicchemistry.chemical_elementContext (language use)DEMO reactorBlanket7. Clean energy01 natural sciences010305 fluids & plasmas0103 physical sciencesWater coolingNeutronicsDEMO reactor; Neutronics; WCLL blanketGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsbusiness.industryMechanical EngineeringWater cooledNuclear powerWCLL blanketNuclear Energy and EngineeringchemistryEnvironmental scienceLithiumbusiness
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Sports contracts in Italy

2010

An article by Mario Serio (Professor of Comparative Law at the University of Palermo, Italy), taken from his presentation at the International Academy of Legal Science conference held at the University of Istanbul in May 2010. The author focuses on the Italian experience of sports contracts and the way relationships between athletes and their employers may be governed in particular legal systems, including protection through implementation within sports bodies. The article is published in Amicus Curiae – Journal of the Society for Advanced Legal Studies at the Institute of Advanced Legal Studies. The Journal is produced by SALS at the Institute of Advanced Legal Studies, University of Londo…

biologyAthletesJurisprudencemedia_common.quotation_subjectContracts sport.General Medicinebiology.organism_classificationLegal sciencePresentationLawPolitical scienceComparative lawLAWCLLmedia_common
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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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