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- W3195002008 abstract "Abstract Sodium Cooled Reactors is one of the Generation-IV plants selected to manage the long-lived minor actinides and to transmute the long-life radioactive elements. This study presents the comparison between two-designed SFR cores with 600 and 800 MW th total heating power. We have analyzed a conceptual core design and nuclear characteristic of SFR. Monte Carlo depletion calculations have been performed to investigate essential characteristics of the SFR core. The core calculations were performed by using the Serpent Monte Carlo code for determining the burnup behavior of the SFR, the power distribution and the effective multiplication factor. The neutronic and burn-up calculations were done by means of Serpent-2 Code with the ENDF-7 cross-sections library. Sodium Cooled Fast Reactor core was taken as the reference core for Th-232 burnup calculations. The results showed that SFR is an important option to deplete the minor actinides as well as for transmutation from Th-232 to U-233." @default.
- W3195002008 created "2021-08-30" @default.
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- W3195002008 date "2021-08-01" @default.
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- W3195002008 title "A Monte Carlo study on burnup treatment in sodium-cooled reactor with Th fuel" @default.
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- W3195002008 doi "https://doi.org/10.1515/kern-2019-0110" @default.
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