Search results for "TRACE Code"

showing 8 items of 8 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 the OSU-MASLWR Natural circulation phenomena using TRACE code

2009

MASLWR TRACE Code Small Modular ReactorSettore ING-IND/19 - Impianti Nucleari
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TRACE and RELAP5 Codes for Beyond Design Accident Condition Simulation in the SPES3 Facility

2012

Code validation on qualified experimental data is a fundamental issue in the design and safety analyses of nuclear power plants. The SPES3 facility is being built at the SIET laboratories for an integral type SMR simulation, in the frame of an R&D program on nuclear fission, funded by the Italian Ministry of Economic Development and led by ENEA. The facility, based on the IRIS reactor design, reproduces the primary, secondary and containment systems with 1:100 volume scale, full elevation and prototypical fluid and thermal-hydraulic conditions. It is suitable to test the plant response to design and beyond design accidents in order to verify the effectiveness of the primary and containm…

Engineeringbusiness.industryNuclear engineeringFrame (networking)Experimental dataNuclear powerTRACE Code RELAP5 code SMR Passive safety Systems Beyond Design Accident ConditionContainmentCabin pressurizationTransient (computer programming)Decay heatbusinessSettore ING-IND/19 - Impianti NucleariSimulationTRACE (psycholinguistics)Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles
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Analysis of the SPES-3 direct vessel injection line break by using TRACE code

2011

TRACE Code thermal-hydraulicsSettore ING-IND/19 - Impianti Nucleari
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TRACE, RELAP5 Mod 3.3, and RELAP5-3D Code Comparison of OSU-MASLWR-001 Test

2009

MASLWRTRACE code Smal Modular ReactorSettore 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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