Search results for "Anti nuclear"

showing 10 items of 415 documents

On the nuclear response of the helium-cooled lithium lead test blanket module in ITER

2005

Abstract The helium-cooled lithium lead (HCLL) concept has been recently selected as one of the two European reference designs foreseen for the breeding blanket of a demonstration fusion reactor. In particular, within the framework of the research and development activities on this blanket line, an HCLL test blanket module (TBM) has to be designed and manufactured to be implemented in ITER. At the Department of Nuclear Engineering (DIN) of the University of Palermo, a research campaign has been carried out to investigate the nuclear response of HCLL-TBM inside ITER by a numerical approach based on the Monte Carlo method. A realistic 3D heterogeneous model of HCLL-TBM has been set-up and ins…

CryostatMaterials scienceMechanical EngineeringNuclear engineeringMonte Carlo methodchemistry.chemical_elementBlanketFusion powerNuclear Energy and EngineeringchemistryTest blanket moduleHCLL-blanketNeutronicsRadiation damageNeutron sourceGeneral Materials ScienceLithiumSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringFusion Engineering and Design
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A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material

2008

Abstract Within the European Fusion Technology Programme, the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept is one of the two EU lines to be developed for a Long Term fusion reactor, in particular with the aim of manufacturing a Test Blanket Module (TBM) to be implemented in ITER. The HCLL-TBM is foreseen to be located in an ITER equatorial port, being housed inside a steel-supporting frame, actively cooled by pressurized water. That supporting frame has been designed to house two different TBMs, providing two cavities separated by a dividing Plate 20 cm thick. As the nuclear response of HCLL-TBM might vary accordingly to the supporting frame configuration and composition, at t…

CryostatNeutron transportMaterials scienceMechanical EngineeringNuclear engineeringFrame (networking)Fusion powerBlanketCoolantNuclear Energy and EngineeringNeutron sourceGeneral Materials ScienceLithium-lead blanket TBM NeutronicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringParametric statisticsFusion Engineering and Design
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Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER

2009

Abstract The present paper deals with the detailed investigation of the helium-cooled lithium lead test blanket module (HCLL-TBM) nuclear behaviour under irradiation in ITER, carried out at the Department of Nuclear Engineering of the University of Palermo adopting a numerical approach based on the Monte Carlo method. A realistic 3D heterogeneous model of the HCLL-TBM was set-up and inserted into an ITER 3D semi-heterogeneous model that realistically simulates the reactor lay-out up to the cryostat. A Gaussian-shaped neutron source was adopted for the calculations. The main features of the HCLL-TBM nuclear response were assessed, paying a particular attention to the neutronic and photonic d…

CryostatNeutron transportTokamakMaterials scienceMechanical EngineeringNuclear engineeringchemistry.chemical_elementFusion powerBlanketHCLL test blanket module Neutronics Monte Carlo methodlaw.inventionNuclear physicsNuclear Energy and EngineeringchemistrylawNeutron sourceGeneral Materials ScienceLithiumSettore ING-IND/19 - Impianti NucleariHeliumCivil and Structural EngineeringFusion Engineering and Design
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MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor

2003

DEMO ReactorNatural ConvectionNuclear FusionHelium Cooled Lithium Lead BlanketMagnetohydrodynamicCFDSettore ING-IND/19 - Impianti Nucleari
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Integrated multi-physics design tool for fusion breeding blanket systems - development and validation

2020

Il Breeding Blanket (BB) del reattore DEMO rappresenta un sistema complesso in un ambiente pericoloso. Infatti, esso deve soddisfare diversi requisiti e vincoli ingegneristici sia di tipo nucleare, termo-strutturale che di sicurezza. Per questi motivi, è necessaria una progettazione omnicomprensiva che preveda l'applicazione di strumenti avanzati di simulazione basati su approcci multi-fisici. Questi strumenti devono eseguire simultaneamente diversi tipi di analisi. Tre di esse possono essere considerate prioritarie e propedeutiche per lo studio di tutti gli altri fenomeni riguardanti il BB, vale a dire l´analisi nucleare, termo-fluidodinamica e strutturale. In questa tesi, è proposto un in…

DEMO ReactorTechnologyBreeding Blanketmulti-physicsthermal-hydraulicthermo-mechanicCFD analysicouplingneutronicDEMOddc:600Settore ING-IND/19 - Impianti Nuclearimechanical analysi
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THERMOFLUID-DYNAMICS OF DEMO DIVERTOR CASSETTE

2023

The divertor is a critical in-vessel component of nuclear fusion reactors, being responsible for the fulfilment of certain fundamental functions for the machine: it must be able to handle the power deposited by charged particle and neutron irradiation, ensure the presence of channels through which the fusion ashes can be removed from the Vacuum Vessel (VV), provide plasma-compatible surfaces, and shield the VV and magnets from nuclear loads. The heat load that can be tolerated by the divertor under normal and off-normal operating conditions is a pivotal parameter when dimensioning a fusion power plant since exceptionally high heat fluxes can be observed in some regions of the divertor, in t…

DEMO Divertor Plasma facing components Thermofluid-dynamics CFD analysisSettore ING-IND/19 - Impianti Nucleari
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Multiphysics Optimization for Water-Cooled Breeding Blanket Design Enhancement

2021

The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fueling. Within such a kind of reactor, the component selected to house the tritium breeding reactions is the breeding blanket, which is further assigned to heat power removal and radiation shielding functions. As a consequence of both its role and position, the breeding blanket is heavily exposed to both surface and volumetric heat loads and, hence, its design requires a typical multiphysics approach, from the neutronics to the thermo-mechanics. During last years, a great deal of effort has been put in the optimization of the breed…

DEMO WCLL Breeding Blanket optimization Complex Method RCC-MRxSettore ING-IND/19 - Impianti Nucleari
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Preliminary design of a Water Cooled Lithium Lead blanket concept for DEMO reactor

2013

DEMOWCLL blanketSettore ING-IND/19 - Impianti Nucleari
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Eurofusion-DEMO Divertor - Cassette Design and Integration

2020

International audience; The Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, named G1, scheduled to take place in Q4 2020 that will focus on assessing the feasibility of the plant and its main components prior to entering into the Conceptual Design phase. In the paper first an overview is given of the Eurofusion-DEMO Divertor Assembly including design and interface description, systems and functional requirements, load specification, system classification, manufacturing procedures and cost estimate. Then critical issues are discussed and potential design solutions are proposed, e.g.:- Neutron material damage limits of the different (structural) mat…

DEMO; Divertor; CAD DesignMaterials sciencePassive coolingNuclear engineeringPort (circuit theory)01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]DivertorConceptual design0103 physical sciencesDEMO fusion reactorGeneral Materials ScienceCAD Design010306 general physicsDEMOnuclear fusionSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineeringelectromagnetic computationToroidNuclear heatingSeparatrixMechanical EngineeringDivertornuclear fusion plasma control electromagnetic computationNuclear Energy and EngineeringTUNGSTEN/EUROFER COATING SYSTEM CONCEPTUAL DESIGN COOLING CIRCUIT PROGRESS HCLLplasma controlHigh heat
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Un nuovo approccio per l’integrazione dell’analisi di rischio nella valutazione degli impatti ambientali connessi alle operazioni di smantellamento d…

2018

La disattivazione e lo smantellamento delle installazioni nucleari a seguito della loro cessazione di esercizio è uno dei problemi che molti paesi si trovano ad affrontare avendo come vincolo la garanzia della sostenibilità ambientale e la sicurezza della popolazione e dei lavoratori coinvolti nelle varie procedure operative. Tuttavia, non esiste allo stato attuale una metodologia capace di classificare la rilevanza dei vari tipi di impatto, ma piuttosto una varietà di strategie che dipendono fortemente dalla normativa vigente nel paese di appartenenza. Ciò ha portato a trascurare la definizione di una procedura capace di individuare proattivamente le condizioni di rischio connesse alle att…

Decommissioning impianti nucleari Environmental Impact Mode and Criticality Analysis Valutazione di Impatto AmbientaleSettore ING-IND/19 - Impianti Nucleari
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