Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor
نویسندگان
چکیده
In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of European Sodium-cooled Fast Reactor. The multiplication factor, conversion delayed neutrons fraction, doppler constant, control rod worth, sodium void masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. results show that reactor breeds fissile isotopes with ratio 0.994 fuel 70 (GWd/T), minor actinides buildup inside core. study aims check efficiency on calculation neutronic parameters core burnup.
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ژورنال
عنوان ژورنال: Baghdad Science Journal
سال: 2022
ISSN: ['2078-8665', '2411-7986']
DOI: https://doi.org/10.21123/bsj.2022.7409