Core and fuel cycle for an advanced sodium-cooled fast reactor |
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| Authors: | V. M. Poplavskii A. M. Tsibulya Yu. S. Khomyakov V. I. Matveev V. A. Eliseev A. G. Tsikunov B. A. Vasil’ev S. B. Belov M. R. Farakshin |
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| Affiliation: | 1.State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI),Obninsk,Russia;2.Afrikantov Experimental Design Bureau of Mechanical Engineering,Nizhnii Novgorod,Russia |
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| Abstract: | The development of BN-1200 is based on the greatest possible use of tested and scientifically validated and developed technical solutions implemented in BN-350, -600, and the BN-800 design as well as new technical solutions that increase facility cost-effectiveness and safety. The BN-1200 design must permit the reactor to operate with different cores, including with denser fuel. The main fuel variant considered is oxide fuel and for the nearest term nitride fuel, for which the production technology involves the same steps as the oxide technology. The main approaches for choosing the parameters of the BN-1200 core as well as the results of computational studies are presented. |
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