Search results for "DEMO Reactor"

showing 5 items of 15 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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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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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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On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module

2014

Within the framework of the European DEMO Breeder Blanket Programme, a research campaign has been launched by University of Palermo, ENEA-Brasimone and Karlsruhe Institute of Technology to theoretically investigate the thermo-mechanical behavior of the Helium-Cooled Pebble Bed (HCPB) breeding blanket module of the DEMO1 blanket vertical segment, under normal operation and over-pressurization loading scenarios. The research campaign has been carried out following a theoretical-computational approach based on the finite element method (FEM) and adopting a qualified commercial FEM code. A realistic 3D FEM model of the HCPB blanket module central poloidal-radial region has been developed, inclu…

ToroidSteady stateThermo-mechanicsMechanical EngineeringNuclear engineeringHCBP blanketThermo-mechanicchemistry.chemical_elementDEMO reactorThermo-mechanics;DEMO reactor;HCBP blanketBlanketFinite element methodCoolantBreeder (animal)Nuclear Energy and EngineeringchemistryThermalDEMO reactor HCBP blanket Thermo-mechanicsEnvironmental scienceGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural Engineering
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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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