Search results for "steam generator"

showing 7 items of 7 documents

Analysis of the Multi-Application Small Light-Water Reactor (MASLWR) Design Natural Circulation Phenomena

2011

database for code validationpressurizationMASLWR experimental facility Oregon State University SMR coupling primary system-containment pressurization database for code validationOregon State Universitycoupling primary system-containmentSMRMASLWR experimental facilityTRACE code MASLWR SMR Helical Coil Steam Generator Natural Circulation Primary/Containment Coupling Passive SystemsSettore ING-IND/19 - Impianti Nucleari
researchProduct

Preliminary Thermo-Mechanical Design of the Once Through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO

2020

The European DEMOnstration power plant (DEMO) is considered to be the nearest-term fusion reactor capable of producing several hundred MWs of net electricity, operating with a closed tritium fuel-cycle (achieving the tritium self-sufficiency), and qualifing technological solutions for a fusion power plant with different breeding blanket (BB) concepts that are under investigation. The BB is a key component for the development of the DEMO plant design and, in particular, of those systems having the responsibility to remove the plasma-generated thermal power and its conversion in the electrical energy. This study deals with the preliminary thermo-mechanical design of the heat exchangers and st…

Nuclear and High Energy PhysicsDEMOnstration power plant (DEMO)Power stationbusiness.industryBoiler (power generation)Thermal power stationFusion powerBlanketCondensed Matter Physics01 natural sciences7. Clean energyGeneralLiterature_MISCELLANEOUS010305 fluids & plasmassteam generatorHeat recovery steam generator0103 physical sciencesHeat exchangerEnvironmental scienceHydraulic machineryProcess engineeringbusinessheat exchangertube sheetBalance of plant (BoP)IEEE Transactions on Plasma Science
researchProduct

Simulazioni Numeriche del Campo di Moto e della Caduta di Pressione in Tubi Elicoidali

2009

TurbulenceHelical CoilSteam GeneratorCurved PipeCFDHeat TransferFluid FlowRANS Turbulence ModelPressure DropIRIS ReactorSettore ING-IND/19 - Impianti Nucleari
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

Analyses of the OSU-MASLWR Experimental Test Facility

2012

Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of importance to multi-application small light water reactor (MASLWR) design, a small modular pressurized water reactor (PWR), relying on natural circulation during both steady-state and transient operation. The target of this paper is to give a review of the main characteristics of the experimental facility, to analyse the main phenomena characteri…

Engineeringbusiness.industryNuclear engineeringPressurized water reactorOSU-MASLWR natural circulation modular PWRExperimental dataEnergy mixModular designnatural circulationlaw.inventionThermal hydraulicsNuclear technologyNatural circulationNuclear Energy and EngineeringlawLight-water reactorlcsh:Electrical engineering. Electronics. Nuclear engineeringOSU-MASLWRmodular PWRbusinesslcsh:TK1-9971Settore ING-IND/19 - Impianti NucleariSimulationMASLWR SMR Best Estimate Thermal Hydraulic System Code Helical Coil Steam Generator Primary/Containment Coupling Natural CircuationScience and Technology of Nuclear Installations
researchProduct

Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE

2011

Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and the evaluation of a code's calculation accuracy is accomplished by assessment and validation against appropriate system data. These system data may be developed either from a running system prototype or from a scaled model test facility, and characterize the thermal hydraulic phenomena during both steady state and transient conditions. The identification and characterization of the relevant thermal hydraulic phenomena, and the assessment and validation of thermal hydraulic systems codes, has been the objective of multiple international research programs. The validation and…

Nuclear and High Energy PhysicsEngineeringbusiness.industryMechanical EngineeringSuperheated steamNuclear engineeringNuclear Engineering Thermal HydraulicBoiler (power generation)System safetyNuclear reactorlaw.inventionThermal hydraulicsNatural circulationNuclear Energy and EngineeringNuclear reactor corelawHeat exchangerForensic engineeringGeneral Materials ScienceSafety Risk Reliability and QualitybusinessWaste Management and DisposalSettore ING-IND/19 - Impianti NucleariTRACE Code MASLWR SMR Helical Coils Steam Generator Natural Circulation
researchProduct

Analysis of the OSU-MASLWR-003A natural circulation test by using the trace code

2012

Advanced small modular integral reactorsAdvanced small modular integral reactors OSU-MASLWR Natural circulation phenomena TRACENatural circulation phenomenaTRACETRACE code MASLWR SMR Natural Circulation Helical Coil Steam GeneratorOSU-MASLWRSettore ING-IND/19 - Impianti Nucleari
researchProduct