Kullanılmış Nükleer Yakıt Depolama Kabının Isıl Analizi
Gökselkınav, Açelya Deniz
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In this study, thermal analysis was performed for the TN-24P cask by using Computational Fluid Dynamics method. For the analysis, ANSYS Fluent as a CFD tool was selected since it has the proper finite volume methods to realistically simulate the thermal behavior of storage casks. The calculations performed with Fluent involve both steady state and transient (accident) simulations and the results of steady state calculations were compared with the data of the experiments related with the TN-24P storage casks.In this study, by taking the simulated experimental study into account, for the analysis, spent fuels discharged from pressurized water reactors (PWRs) were modeled. In the model, there are 24 PWR spent fuel assemblies loaded in the TN-24P cask. Spent nuclear fuels were lumped 3x3 on modeling. For the dry cask analysis, simulation of accident conditions is required. In this study, air blockage accident which causes increase in the temperatures in the cask is also simulated.