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This study presents regression analysis method used for prediction and investigation of neutronic performance in a hybrid reactor using UO2 fuel and Flibe (Li2BeF4) coolant. The 235U fraction is increased gradually from 0 to 4% stepped by 1% and the 6Li fraction within the Flibe coolant is enriched gradually to 30, 60 and 90% from 7.5%. Relations between 235U fuel fraction and lithium (6Li) enrichment...
In design a Deuterium–Tritium (D–T) fusion driven hybrid reactor, neutronics and nuclear data libraries have an essential role for reliable neutronics calculations. Therefore, nuclear data libraries are very important to calculate of the neutronic parameters and selection of tritium breeder materials to be used in the blanket. In this study tritium breeding performances of candidate tritium breeding...
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