On-Site Nuclear Fuel Cycle of “BREST” Reactors
International Journal of Energy and Power Engineering
Volume 7, Issue 1, February 2018, Pages: 1-5
Received: Oct. 23, 2017; Accepted: Dec. 19, 2017; Published: Feb. 1, 2018
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Authors
Andrei Gennadevich Glazov, Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”, Moscow, the Russian Federation
Yury Sergeevich Khomyakov, Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”, Moscow, the Russian Federation
Maksim Konstantinovich Gorbachev, Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”, Moscow, the Russian Federation
Leonid Petrovich Sukhanov, Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”, Moscow, the Russian Federation
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Abstract
Dynamic developing of modern nuclear industry demands meeting the following requirements: improved safety, reduced capital costs, radioactive waste (RW) management issues, independence of limited resources. Efficiency of uranium resources used in "BREST" reactors based on a closed fuel cycle is about 160 times higher than for VVER, RBMK reactors [1], which makes it possible to stop searching for new deposits and uranium mining. The need for periodical fuel regeneration and fabrication in a closed cycle includes reproduction of plutonium in the core without the uranium containing screens (breeding ratio is approximately 1,05, ensuring a high level of safety and support of the non-proliferation regime) and transmutation of the most dangerous long-lived actinides and high refining of RW, achieving the radiation balance of buried RW and extracted uranium ore. The manufacturing is located directly at the NPP to avoid transportation of fissile materials. This approach provides economic efficiency of the entire complex.
To cite this article
Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov, On-Site Nuclear Fuel Cycle of “BREST” Reactors, International Journal of Energy and Power Engineering. Vol. 7, No. 1, 2018, pp. 1-5. doi: 10.11648/j.ijepe.20180701.11
Copyright
Copyright © 2018 Authors retain the copyright of this article.
This article is an open access article distributed under the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0/) which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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