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Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor

Mohamed, Nehal ; Aziz, Moustafa ; El Ghazaly, M. ; Bashter, Ibrahim

Majallat Baghdād lil-ʻulūm, 2022-12, Vol.19 (6(Suppl.)), p.1551

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Título:
Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor
Autor: Mohamed, Nehal ; Aziz, Moustafa ; El Ghazaly, M. ; Bashter, Ibrahim
É parte de: Majallat Baghdād lil-ʻulūm, 2022-12, Vol.19 (6(Suppl.)), p.1551
Descrição: In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of the European Sodium-cooled Fast Reactor. The multiplication factor, conversion factor, delayed neutrons fraction, doppler constant, control rod worth, sodium void worth, masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. The results show that the reactor breeds fissile isotopes with a conversion ratio of 0.994 at fuel burnup 70 (GWd/T), and minor actinides are buildup inside the reactor core. The study aims to check the efficiency of the model on the calculation of the neutronic parameters of the core at high burnup.
Editor: College of Science for Women, University of Baghdad
Idioma: Inglês;Árabe

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