Abstract
Abstract This work consists of a preliminary development of a Small Fast Sodium Reactor (SFSR) proposal based on 4S Reactor project and SSTAR (Small Secure Transportable Reactor) concept. Neutronic parameters such as burnup behavior, depletion fuel composition, absorbing elements, core reactivity control and reactivity coefficients that affect the reactor cooled by sodium along its operation cycle have been analyzed. The parameters are evaluated in terms of the reactivity coefficients at different cycle stages. The results present a comparison and discussion of the differences found between the model developed and some information available in the literature for similar projects. The neutronic evaluation was performed using the MCNPX code.
Published Version
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