On-Site Nuclear Fuel Cycle of “BREST” Reactors

Andrei Gennadevich Glazov; Yury Sergeevich Khomyakov; Maksim Konstantinovich Gorbachev; Leonid Petrovich Sukhanov

doi:doi:10.11648/j.ijepe.20180701.11

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On-Site Nuclear Fuel Cycle of “BREST” Reactors

Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov

Published in International Journal of Energy and Power Engineering (Volume 7, Issue 1)

Received: 23 October 2017 Accepted: 19 December 2017 Published: 1 February 2018

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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.

Published in	International Journal of Energy and Power Engineering (Volume 7, Issue 1)
DOI	10.11648/j.ijepe.20180701.11
Page(s)	1-5
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2024. Published by Science Publishing Group

Keywords

Closed Nuclear Fuel Cycle, Nuclear Energy, Fast Reactor

References

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[2]	E. Adamov, I. Ganev, A. Lopatkin, et al., “Transmutation Fuel Cycle in Largescale Nuclear Power of Russia”, Monograph, Publishing house of JSC N. A. Dollezhal Research and Development Institute of Power Engineering, Moscow, 1999 (in Russian).
[3]	E. Muravyov, Relevance of Nuclear Fuel Cycle Closing, Nuclear Energy, volume 111, № 6, Moscow, 2011 (in Russian).
[4]	E. Adamov, A. Dzhalavyan, A. Lopatkin, N. Molokanov, E. Muravyov, V. Orlov, S. Kalyakin, V. Rachkov, V. Troyanov, E. Avrorin, V. Ivanov, R. Aleksahin, Conceptual Issues of Nuclear Power Development Strategy in Russia in the 21^st Century, Nuclear Energy, volume 112, № 6, Moscow, 2012 (in Russian).
[5]	M. Radchenko, A. Shadrin, P. Poluektov, O. Shmidt, A. Tuzov, Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors with Liquid-Metal Coolant, Nuclear Energy, volume 115, № 2, Moscow, 2013 (in Russian).
[6]	V. Troyanov, A. Grachev, L. Zabudko, M. Skupov, Prospects for Using Nitride Fuel in Fast Reactors with a Closed Nuclear Fuel Cycle, Nuclear Energy, volume 117, № 2, Moscow, 2014 (in Russian).
[7]	V. Troyanov, A. Grachev, L. Zabudko, M. Skupov, D. Zozulya, Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors, Nuclear Energy, volume 118, № 2, Moscow, 2015 (in Russian).
[8]	A. Grachev, L. Zabudko, A. Glushenkov, Yu. Ivanov, G. Kireev, M. Skupov, I. Gilmutdinov, P. Grin, E. Zvir, F. Kryukov, O. Nikitin, Research of Mixed Nitride Uranium-Plutonium Fuel within the Framework of «Proryv» Project, Nuclear Energy, volume 122, № 3, Moscow, 2017 (in Russian).
[9]	IAEA Nuclear Energy Series No. NP-T-1.6. Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic, Vienna, 2012.
[10]	A. Shadrin, V. Ivanov, M. Skupov, V. Troyanov, A. Zherebtsov, Comparison of Closed Nuclear Fuel Cycle Technologies, Nuclear Energy, volume 121, № 2, Moscow, 2016 (in Russian).
[11]	A. Shadrin, K. Dvoeglazov, A. Maslennikov, V. Kashcheev, S. Tretyakova, O. Shmidt, V. Vidanov, O. Ustinov, V. Volk, S. Veselov, V. Ishunin, РH Process as a Technology for Reprocessing Mixed Uranium-Plutonium Fuel From BREST-OD-300 reactor, Radiochemistry, volume 58, № 3, Moscow, 2016 (in Russian).

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APA Style

Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov. (2018). On-Site Nuclear Fuel Cycle of “BREST” Reactors. International Journal of Energy and Power Engineering, 7(1), 1-5. https://doi.org/10.11648/j.ijepe.20180701.11

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ACS Style

Andrei Gennadevich Glazov; Yury Sergeevich Khomyakov; Maksim Konstantinovich Gorbachev; Leonid Petrovich Sukhanov. On-Site Nuclear Fuel Cycle of “BREST” Reactors. Int. J. Energy Power Eng. 2018, 7(1), 1-5. doi: 10.11648/j.ijepe.20180701.11

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AMA Style

Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov. On-Site Nuclear Fuel Cycle of “BREST” Reactors. Int J Energy Power Eng. 2018;7(1):1-5. doi: 10.11648/j.ijepe.20180701.11

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@article{10.11648/j.ijepe.20180701.11,
  author = {Andrei Gennadevich Glazov and Yury Sergeevich Khomyakov and Maksim Konstantinovich Gorbachev and Leonid Petrovich Sukhanov},
  title = {On-Site Nuclear Fuel Cycle of “BREST” Reactors},
  journal = {International Journal of Energy and Power Engineering},
  volume = {7},
  number = {1},
  pages = {1-5},
  doi = {10.11648/j.ijepe.20180701.11},
  url = {https://doi.org/10.11648/j.ijepe.20180701.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20180701.11},
  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.},
 year = {2018}
}

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TY  - JOUR
T1  - On-Site Nuclear Fuel Cycle of “BREST” Reactors
AU  - Andrei Gennadevich Glazov
AU  - Yury Sergeevich Khomyakov
AU  - Maksim Konstantinovich Gorbachev
AU  - Leonid Petrovich Sukhanov
Y1  - 2018/02/01
PY  - 2018
N1  - https://doi.org/10.11648/j.ijepe.20180701.11
DO  - 10.11648/j.ijepe.20180701.11
T2  - International Journal of Energy and Power Engineering
JF  - International Journal of Energy and Power Engineering
JO  - International Journal of Energy and Power Engineering
SP  - 1
EP  - 5
PB  - Science Publishing Group
SN  - 2326-960X
UR  - https://doi.org/10.11648/j.ijepe.20180701.11
AB  - 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.
VL  - 7
IS  - 1
ER  -

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Author Information

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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APA Style

Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov. (2018). On-Site Nuclear Fuel Cycle of “BREST” Reactors. International Journal of Energy and Power Engineering, 7(1), 1-5. https://doi.org/10.11648/j.ijepe.20180701.11

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ACS Style

Andrei Gennadevich Glazov; Yury Sergeevich Khomyakov; Maksim Konstantinovich Gorbachev; Leonid Petrovich Sukhanov. On-Site Nuclear Fuel Cycle of “BREST” Reactors. Int. J. Energy Power Eng. 2018, 7(1), 1-5. doi: 10.11648/j.ijepe.20180701.11

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AMA Style

Andrei Gennadevich Glazov, Yury Sergeevich Khomyakov, Maksim Konstantinovich Gorbachev, Leonid Petrovich Sukhanov. On-Site Nuclear Fuel Cycle of “BREST” Reactors. Int J Energy Power Eng. 2018;7(1):1-5. doi: 10.11648/j.ijepe.20180701.11

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@article{10.11648/j.ijepe.20180701.11,
  author = {Andrei Gennadevich Glazov and Yury Sergeevich Khomyakov and Maksim Konstantinovich Gorbachev and Leonid Petrovich Sukhanov},
  title = {On-Site Nuclear Fuel Cycle of “BREST” Reactors},
  journal = {International Journal of Energy and Power Engineering},
  volume = {7},
  number = {1},
  pages = {1-5},
  doi = {10.11648/j.ijepe.20180701.11},
  url = {https://doi.org/10.11648/j.ijepe.20180701.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20180701.11},
  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.},
 year = {2018}
}

Copy | Download

TY  - JOUR
T1  - On-Site Nuclear Fuel Cycle of “BREST” Reactors
AU  - Andrei Gennadevich Glazov
AU  - Yury Sergeevich Khomyakov
AU  - Maksim Konstantinovich Gorbachev
AU  - Leonid Petrovich Sukhanov
Y1  - 2018/02/01
PY  - 2018
N1  - https://doi.org/10.11648/j.ijepe.20180701.11
DO  - 10.11648/j.ijepe.20180701.11
T2  - International Journal of Energy and Power Engineering
JF  - International Journal of Energy and Power Engineering
JO  - International Journal of Energy and Power Engineering
SP  - 1
EP  - 5
PB  - Science Publishing Group
SN  - 2326-960X
UR  - https://doi.org/10.11648/j.ijepe.20180701.11
AB  - 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.
VL  - 7
IS  - 1
ER  -

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