Search results for " MASLWR"

showing 5 items of 5 documents

TRACE Analysis of the MASLWR Primary/Containment Coupling Phenomena in Beyond Design Accident Scenario

2013

SBLOCATRACEOSU-MASLWROSU-MASLWR SBLOCA TRACETRACE Code MASLWR Beyond Design Accident Scenario Primary/Containment CouplingSettore ING-IND/19 - Impianti Nucleari
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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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Analysis of Primary/Containment Coupling Phenomena Characterizing the MASLWR Design During a SBLOCA Scenario

2012

Today considering the world energy demand increase, the use of advanced nuclear power plants, have an important role in the environment and economic sustainability of country energy strategy mix considering the capacity of nuclear reactors of producing energy in safe and stable way contributing in cutting the CO2 emission (Bertel & Morrison, 2001; World Energy Outlook-Executive Summary, 2009; Wolde-Rufael & Menyah, 2010; Mascari et al., 2011d). According to the information’s provided by the “Power Reactor Information System” of the International Atomic Energy Agency (IAEA), today 433 nuclear power reactors are in operation in the world providing a total power installed capacity of 366.610 G…

Primary/Containment Coupling MASLWR SBLOCAEnergy demandbusiness.industrySMR MASLWR TRACE Primary/Containment Coupling SBLOCAShutdownAtomic energyNuclear engineeringMASLWRSBLOCANuclear powerNameplate capacityCoupling (computer programming)ContainmentInformation systemPrimary/Containment CouplingEnvironmental sciencebusinessSettore ING-IND/19 - Impianti Nucleari
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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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