Search results for "Anti nuclear"

showing 10 items of 415 documents

Entropy, Benford’s first digit law, and the distribution of everything

2010

Shannon entropy probability density function size distribution Benford lawSettore ING-IND/19 - Impianti Nucleari
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Assessment of Fatigue Effects Induced by Fast Beam Transients in the IFMIF-DONES Li Target

2020

One of the crucial steps toward the commercial exploitation of fusion energy is the availability of a high-intensity neutron source able to test and qualify structural materials to be used in future fusion power reactors. The International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES) facility, which is currently being designed within the framework of the EUROfusion Consortium, represents the European effort to develop such a neutron source. It employs a liquid lithium target struck by an accelerated deuteron (D+) beam to produce fusion-like neutrons used to irradiate materials samples. So far, a detailed investigation of the thermomechanical behavior of t…

Shock waveNuclear and High Energy PhysicsMaterials scienceNuclear engineeringchemistry.chemical_element7. Clean energy01 natural sciences010305 fluids & plasmasBeam trips0103 physical sciencesNeutronlithium targetSettore ING-IND/19 - Impianti NucleariStructural materialInternational Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES)shock wavesFusion powerCondensed Matter Physics3. Good healthchemistry13. Climate actionNeutron sourceLithiumfatigueBeam (structure)Nominal power (photovoltaic)IEEE Transactions on Plasma Science
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Implementazione ed utilizzo di simulatori semplificati “Desktop”

2011

Simulatori reattoriSettore ING-IND/19 - Impianti Nucleari
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Analisi di Sistemi Passivi, Utilizzati in Impianti ad Acqua Pressurizzata di Tipo Avanzato. Identificazione di Componenti di Piccolo Diametro

2011

Sistemi passivi PWRSettore ING-IND/19 - Impianti Nucleari
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Identificazione Di Componenti Di Piccola Taglia In Sistemi Di Tipo Passivo e Possibili Attività Sperimentali Per La Loro Caratterizzazione

2011

Sistemi passiviSettore ING-IND/19 - Impianti Nucleari
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2018

A vigorous anti-nuclear movement emerged in Germany in the mid 1990s, when spent nuclear fuel elements began to be transported to the interim storage facility in Gorleben, Lower Saxony. Resistance ...

Sociology and Political Sciencemedia_common.quotation_subjectAnti nuclearfood and beveragesRadioactive wasteLower saxonySpent nuclear fuellanguage.human_languageDemocracyGermanPolitical economyInterimPolitical sciencelanguagemedia_commonParliaments, Estates and Representation
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Termoidraulica del sodio - elementi teorici e sperimentali

1982

SodiumThermal HydraulicFast Breeder ReactorLiquid MetalHeat TransferFluid FlowNuclear Reactor CoolantSettore ING-IND/19 - Impianti Nucleari
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Heat-transfer performance comparison between overlapped and woven spacers for membrane distillation

2016

Sustainable production of fresh water from seawater desalination is a problem of crucial importance nowadays. Recently, some desalination technologies are taking advantage from the coupling with renewable resources. Among emerging technologies, Membrane Distillation (MD) is considered as one of the most promising as it can be easily powered by solar thermal energy or waste-heat. As an emerging technology, efforts are required to optimize MD unit geometry and operating conditions in order to reduce fresh water production specific cost. Temperature polarization phenomenon is a well-known detrimental effect for the MD process. Spacers are traditionally used to enhance mixing and shrink tempera…

Spacer Membrane Separation processesSettore ING-IND/26 - Teoria Dello Sviluppo Dei Processi ChimiciSettore ING-IND/19 - Impianti Nucleari
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Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out

2013

Station Black-out fission reactorsSettore ING-IND/19 - Impianti Nucleari
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On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module

2016

Abstract Within the framework of EUROfusion R&D activities a research campaign has been carried out at the University of Palermo in order to investigate the thermo-mechanical performances of the DEMO water-cooled lithium lead (WCLL) breeding blanket first wall (FW). The research campaign has been mainly focused on the optimization of the FW geometric configuration in order to maximize the heat flux it may safely withstand fulfilling all the thermal, hydraulic and mechanical requirements foreseen by safety codes. Attention has been focused on the FW flat concept endowed with square cooling channels and the potential influence of its four main geometrical parameters on its thermo-mechanical p…

Steady stateComputer scienceMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences7. Clean energyFinite element methodSquare (algebra)010305 fluids & plasmasDEMO reactor WCLL blanket First wallNuclear Energy and EngineeringHeat fluxchemistry0103 physical sciencesThermalGeneral Materials ScienceLithium010306 general physicsLead (electronics)Settore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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