IAEA R&D Activities in Support of the Innovative Fast Reactor ...
IAEA R&D Activities in Support of the Innovative Fast Reactor ...
IAEA R&D Activities in Support of the Innovative Fast Reactor ...
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<strong>IAEA</strong> Coord<strong>in</strong>ated Research <strong>Activities</strong> on FRsCRPs on <strong>Fast</strong> <strong>Reactor</strong> TechnologyCRPs recentlycompletedCRPs currentlyon-go<strong>in</strong>gCRPs plannedAnalytical and Experimental BenchmarkAnalyses <strong>of</strong> Accelerator Driven Systems (ADS)Analyses <strong>of</strong>, and Lessons Learned from, <strong>the</strong>Operational Experience with <strong>Fast</strong> <strong>Reactor</strong>Equipment and SystemsControl Rod Withdrawal and Sodium NaturalCirculation Tests Performed Dur<strong>in</strong>g <strong>the</strong>PHENIX End-<strong>of</strong>-Life Tests<strong>IAEA</strong>Benchmark Analyses <strong>of</strong> Sodium NaturalConvection <strong>in</strong> <strong>the</strong> Upper Plenum <strong>of</strong> <strong>the</strong>MONJU <strong>Reactor</strong> VesselBenchmark Analyses <strong>of</strong> an EBR-IIShutdown Heat Removal TestSodium Properties and Design and SafeOperation <strong>of</strong> Experimental Facilities <strong>in</strong><strong>Support</strong> <strong>of</strong> <strong>the</strong> Development andDeployment <strong>of</strong> Sodium-cooled <strong>Fast</strong><strong>Reactor</strong>s (SFR) - NAPROSource Term for RadioactivityRelease Under <strong>Fast</strong> <strong>Reactor</strong> CoreDisruptive Accident (CDA)SituationsBenchmark exercise on NeutronicCalculations for a Mixed-oxideFuelled Core <strong>of</strong> an Industrial SizeSodium-cooled <strong>Fast</strong> <strong>Reactor</strong>
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