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This repository hosts all the analysis documentation related to the design of a 'Sodium Cooled Fast reactor Fuel Pin' using a 1-1/2D approach.

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Sodium Cooled Fast Reactor' Fuel Pin 1-1/2 D Analysis

This project was developed during the last year of MSc. at 'Politecnico di Milano' for the 'Nuclear Design and Technology' course.

The goal of the project was to perform a complete thermo-mechanical 1-1/2 D analysis in order to design a fuel pin for a SFR similar to the ASTRID concept. After a complete evaluation of all the main processes involved, is proposed a set of possible parameters in order to respect physical constraints and regulations limits. These parameters are: gap size, cladding thickness and plenum volume.

The numerical simulations were made using the Colab IDLE Python envinronment.

The theoretical frame and the procedure followed for the code development, together with the results obtained, is here available in the attached paper.

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This repository hosts all the analysis documentation related to the design of a 'Sodium Cooled Fast reactor Fuel Pin' using a 1-1/2D approach.

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