Abstract
This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this code, the new model of residual heat removal was created for the SKODA 1000/19 cask where the spent nuclear fuel TVSA-T type from NPP Temelin will be stored. The object of calculations was to obtain the inside temperatures under maximum loads. After that, the results were compared to the requirements of the local regulatory body. Because of the absence of experimental data, the validation of the created computational models could not be accomplished. However, according to the verification scheme of the COBRA-SFS authors, the verification of the new models was implemented.
Highlights
A steel cask is a multifunctional system for storing and for transporting spent fuel. It has to guarantee the cooling of fuel assemblies. This requirement is of primary importance to fuel integrity preservation and, from the regulatory point of view, it is fulfilled if cladding temperature is below the prescribed limit of 350 °C in the Czech Republic which is in agreement with IAEA safety guides [1]
The thermo-fluid dynamics of spent fuel storage casks are a key aspect of safety analyses
The maximum temperature is located in the centre of middle fuel assembly in the case of loading schemes A and B
Summary
A steel cask is a multifunctional system for storing and for transporting spent fuel. This requirement is of primary importance to fuel integrity preservation and, from the regulatory point of view, it is fulfilled if cladding temperature is below the prescribed limit of 350 °C in the Czech Republic which is in agreement with IAEA safety guides [1] In this frame, the thermo-fluid dynamics of spent fuel storage casks are a key aspect of safety analyses. COBRA-SFS retains all the important features of the COBRA codes for single-phase analysis, and extends the range of application to problems with two-dimensional radiative and three-dimensional conductive heat transfer to allow analyses of multiassembly spent-fuel storage and transportation systems (currently the newest version - cycle 4 came out [6]). The authors of the code guarantee errorless function, the correct application brings problems that are not discussed in the available literature
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