Search results for " natural circulation"

showing 4 items of 4 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
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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
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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
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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
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