Search results for " Beyond Design Accident Condition"

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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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