3rd Meeting of the “European MELCOR User Group“ ENEA, Bologna, Italy April 11-12, 2011 TitleSpeakerAgenda List of Participants Fukushima Accident DescriptionM. SangiorgiEstimate of Reflood Times and Flow-Rates for Spent Fuel Pool to Avoid Breakaway Oxidation of Cladding based on MELCOR DataG. L. HorvathCalculations regarding the Spent Fuel Pool ProblemB. S. JaeckelMELCOR validation against Experiments on Hydrogen DistributionJ. DuspivaMELCOR validation against Experiments on Hydrogen DeflagrationJ. DuspivaInvestigations of Gas stratification break-up in Containment for reactor safety issuesJ. C. BirchleyMELCOR Code Development Status, Code Assessment, and QAL. L. HumphriesExperiences with MELCOR 1.8.6 for Level 2 PSA Plant AnalysesT. SteinroetterModelling of Molten-Corium Concrete Interaction using MELCOR 1.8.6B. S. JaeckelMELCOR 2.1 Code performance improvementN. MosunovaComparing results starting from an identical problem descriptionM. SangiorgiDevelopment of an expert system VEHAS. PhilipovMELCOR 1.8.6 Thermal Hydraulic and Iodine Release Calculations for a Small LOCA Initiated Severe Accident with Accident Mitigation MeasuresG. L. HorvathOverview of 2010 CIEMAT Activities involving the MELCOR CodeC. LopezMELCOR post-processing using open source toolsP. Vokac Contact Nuclear Energy and Safety (NES)Laboratory for Reactor-Physics and Thermal Hydraulics (LRT)Severe Accident Research Group (SACRE)Paul Scherrer Institute5232 Villigen PSISwitzerland Mateusz MalickiOffice: OHSA/C02+41 56 310 2127mateusz.malicki@psi.ch
