Search results for " Structural"

showing 10 items of 1751 documents

Hydraulic characterization of the full scale divertor cassette prototype

2011

In the frame of the activities related to ITER divertor R&D, ENEA C.R. Brasimone was in charge by Fusion For Energy (F4E) to perform the assembly, the hydraulic tests and the theoretical simulation of the hydraulic behavior of the full scale divertor cassette prototype. The objective of these activities was aimed at the investigation of the thermal-hydraulic behavior of the full-scale divertor cassette both under steady state condition and during draining and drying operational transient. In particular, the steady state tests were focused on finally check whether the hydraulic design of the divertor components is able to ensure a uniform and proper cooling for the plasma facing components, …

System codeNuclear Energy and EngineeringITER Divertor Draining and dryingMechanical EngineeringNuclear engineeringDivertorFull scaleEnvironmental scienceGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
researchProduct

Hand verification for flexural strength of existing R.C. floors subject to degradation phenomena

2015

Abstract In the present paper, a simplified model for hand verification of the flexural and shear strength of existing corroded T beams cast in place of lightened R.C. orthotropic slabs forming floors is presented and discussed. Diffused and pitting corrosion on steel bars, compressive concrete strength degradation and concrete bond strength degradation are included in the model. The original contribution of the paper is evaluation of the flexural and shear strength considering both the cases of strain compatibility and absence of compatibility and considering the main parameters governing the corrosion process. An arch-resistant model for the calculus of the flexural and shear strength of …

T-beamMaterials scienceBond strengthbusiness.industryPittingBuilding and ConstructionStructural engineeringOrthotropic materialCorrosionCorrosionFlexural strengthCompatibility (mechanics)Pitting corrosionArch strength mechanismR.C. floorT beamComposite materialbusinessBondBeam (structure)Civil and Structural EngineeringCase Studies in Structural Engineering
researchProduct

A Viscoelastic Model for the Long-Term Deflection of Segmental Prestressed Box Girders

2017

Most of segmental prestressed concrete box girders exhibit excessive multidecade deflections unforeseeable by past and current design codes. To investigate such a behavior, mainly caused by creep and shrinkage phenomena, an effective finite element (FE) formulation is presented in this article. This formulation is developed by invoking the stationarity of an energetic principle for linear viscoelastic problems and relies on the Bazant creep constitutive law. A case study representative of segmental prestressed concrete box girders susceptible to creep is also analyzed in the article, that is, the Colle Isarco viaduct. Its FE model, based on the aforementioned energetic formulation, was succ…

TAComputational Theory and MathematicsCivil and Structural Engineering; Computer Science Applications1707 Computer Vision and Pattern Recognition; Computer Graphics and Computer-Aided Design; Computational Theory and MathematicsComputer Science Applications1707 Computer Vision and Pattern RecognitionComputer Graphics and Computer-Aided DesignCivil and Structural Engineering
researchProduct

Random vibration TLCD controlled

2012

TLCD structural control
researchProduct

Divertor of the European DEMO: Engineering and technologies for power exhaust

2022

International audience; In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reaction and external heating must be exhausted through the narrow area of the divertor targets. The targets must withstand the intense bombardment of the diverted particles where high heat fluxes are generated and erosion takes place on the surface. A considerable amount of volumetric nuclear heating power must also be exhausted. To cope with such an unprecedented power exhaust challenge, a highly efficient cooling capacity is required. Furthermore, the divertor must fulfill other critical functions such as nuclear shielding and channeling (and compression) of exhaust gas fo…

Technology020209 energyMechanical EngineeringPower exhaust02 engineering and technologyDEMO; Fusion reactor; Divertor; Plasma-facing component; High-heat-flux; Power exhaust01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]Fusion reactorDivertorDEMO; Divertor; Fusion reactor; High-heat-flux; Plasma-facing component; Power exhaustNuclear Energy and Engineering0103 physical sciences0202 electrical engineering electronic engineering information engineeringPlasma-facing componentGeneral Materials ScienceHigh-heat-fluxddc:600DEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
researchProduct

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
researchProduct

Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code

2021

Abstract In the frame of the activities promoted and encouraged by the EUROfusion Consortium aimed at developing the EU-DEMO fusion reactor, great emphasis has been placed at a very early stage of the design to incorporate the provisions needed to improve the overall plant safety and reliability performances as well as to analyse possible mitigation actions. In this framework, the research activity has been focused on the representative and safety relevant cooling loop of the Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) Primary Heat Transfer System (PHTS), purposely selected by the safety team, in order to assess its thermal-hydraulic behaviour during normal operational conditions …

TechnologyComputer science020209 energyNuclear engineeringHCPBchemistry.chemical_element02 engineering and technologyBlanket7. Clean energy01 natural sciences010305 fluids & plasmasThermal hydraulicsReliability (semiconductor)0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials ScienceRELAP5-3DSafety and EnvironmentHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateFinite volume methodMechanical EngineeringFusion powerEU-DEMONuclear Energy and EngineeringchemistryThermal-hydraulicsHeat transferddc:600
researchProduct

Systems Engineering approach in support to the breeding blanket design

2019

Abstract Nowadays the Systems Engineering (SE) methodology is applied in several fields of engineering and it represents a powerful interdisciplinary means to enable the realisation of complex systems taking into account the customer and Stakeholder´s needs. Also in the fusion community, this theme is becoming increasingly pressing and the implementation of the SE approach, from the early stage of design, is now a must. Indeed, within the framework of EUROfusion activities, SE method has been selected for capturing the system and interface requirements and for their management and verification with particular focus to the Breeding Blanket (BB) System of the European Demonstration Fusion Pow…

TechnologyInterface (Java)Computer scienceSystems EngineeringBalance of plantComplex systemBlanket01 natural sciences7. Clean energy010305 fluids & plasmasSystems Modeling Language0103 physical sciencesGeneral Materials Science010306 general physicsCivil and Structural EngineeringFocus (computing)Functional architectureMechanical EngineeringRealisationInterfaceDesign phaseRequirementNuclear Energy and EngineeringSystems engineeringBreeding blanketddc:600
researchProduct

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
researchProduct

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
researchProduct