0000000000229698

AUTHOR

F. D'auria

showing 4 related works from this author

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, by RELAP5 code, of Boron Dilution Phenomena in Small Break LOCA and in Mid Loop Operation Transients, Performed in PKL III Test Facility

2008

Nuclear Engineering Thermal HydraulicSettore 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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Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR

2014

In the short term period the use of advanced Small Modular Reactor (SMR) is one of the most promising options for the deployment of nuclear technology. The validation and assessment of the best estimate thermal hydraulic system code TRACE against SMR thermal hydraulic phenomena is a novel effort. In this framework the use of the natural circulation database developed at the OSU-MASLWR test facility, simulating the MASLWR reactor prototype, is of interest for analyses of the TRACE code capability in predicting natural circulation and primary/containment coupled behavior in SMR. The target of this paper is to analyze the TRACE V5 capability for the simulation of natural circulation phenomena,…

Thermal hydraulicsEngineeringNatural circulationPrimary (chemistry)ContainmentCoupling (computer programming)business.industryNuclear engineeringMass flow ratebusinessSimulationTRACE (psycholinguistics)Small modular reactor
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