The danger of the wastes from the reprocessing of spent nuclear fuel is largely determined by the presence in them of long-lived actinides, first of all, americium and curium. The solution to the problem could be to involve together with plutonium its attendant actinides in the fuel cycle of fast reactors. This article considers the technologies (reactor, fuel fabrication, and spent fuel reprocessing) that are necessary for burning actinides as part of mixed uranium-plutonium nitride fuel. It is shown that the concentration of actinides, produced in a fast reactor, in the fuel will not exceed 0.5% h.a. For the transmutation of actinides separated from VVER spent fuel simultaneously with plutonium, it is expedient to increase the americium proportion in the fuel to 1.2%. Consideration is given to the possibility of using carbothermal synthesis of the initial powders and tablet technology for the manufacture of mixed uranium-plutonium nitride fuel, as well as the combined technology of spent-fuel reprocessing, planned for realization at a pilot-demonstration power complex with the BREST-300 reactor, and their suitability for involving neptunium and americium in the fuel cycle along with plutonium and uranium.
Similar content being viewed by others
References
E. O. Adamov and V. I. Rachkov, “New technological platform for forming a national strategy for the development of nuclear energy,” Izv. Ross. Akad. Nauk. Energet., No. 2, 3–12 (2017).
M. V. Khramtsov, “Experience in the use of MOX fuel in foreign light-water reactors: status of preparations for the introduction of MOX fuel into VVER-1000 reactors,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Novye Mater., No. 1(72), 6–13 (2012).
P. N. Alekseev, E. A. Bobrov, and A. V. Chibinyaev, “ Multiple recycling of REMIX fuel during VVER-1000 operation in a closed fuel cycle,” Vopr. At. Nauki Tekhn. Ser. Yad. Reakt., No. 4, 115–126 (2014).
P. M. Gavrilov, O. V. Kryukov, K. V. Ivanov, et al., Patent for Invention RU 2702234 C1, “REMIX – nuclear fuel cycle,” Oct. 7, 2019, Application No. 2019108804, March 26, 2019.
V. V. Ignatiev, S. S. Abalin, M. Yu. Gurov, et al., “Reactor with circulating fuel based on metal fluoride melts for burning Np, Am, Cm,” At. Energiya, 129, No. 3, 130–134 (2020).
L. I. Ponomarev, M. N. Belonogov, I. A. Volkov, et al., “Fast molten salt reactor based on the eutectic LIF–NAF–KF as Np, Am, Cm incinerator,” At. Energiya, 126, No. 3, 123–131 (2019).
N. N. Ponomarev-Stepnoi (ed.), Two-Component Nuclear Power System with Thermal and Fast Reactors in a Closed Nuclear Fuel Cycle, Tekhnosfera, Moscow (2016).
A. Yu. Petrov, A. V. Shutikov, and N. N. Ponomarev-Stepnoi, “Prospects for creating a two-component nuclear power system,” Izv. Vuzov. Yad. Energet., No. 2,. 5–15 (2019).
V. M. Dekusar, A. L. Moseev, and P. A. Moseev, “Characteristics of fuel cycles of nuclear power systems based on the joint operation of fast and thermal reactors,” Vopr. At. Nauki Tekhn. Ser. Yad.-Fiz. Konst., No. 3, 210–221 (2017).
D. A. Klinov, A. V. Gulevich, V. A. Elissev, et al., “Possibility of upgrading plutonium in BN-800,” Vopr. At. Nauki Tekhn. Ser. Yad.-Fiz. Konst., No. 2, 15–21 (2020).
A. V. Egorov, Yu. S. Khomyakov, V. I. Rachkov , et al., “Minor actinides transmutation in equilibrium cores of next generation FRs,” Nucl. Energy Technol., 5, No. 4, 353–359 (2019).
G. N. Vlaskin, V. I. Rachkov, and Yu. S. Khomyakov, “Neutron-physical substantiation of Np, Am, Cm transmutation,” At. Energiya, 116, No. 5, 262–266 (2014).
I. V. Bur’evskii, V. A. Eliseev, and I. Yu. Krivitskii, Conceptual Studies of the Use of ROX Fuel in Fast Sodium Power Reactors, Preprint FEI 2958 (2002).
A. Shadrin, K. Dvoeglazov, and V. Kasheev, “PH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor,” Radiochemistry, 58, No. 3, 234–241 (2016).
A. Shadrin, K. Dvoeglazov, and V. Ivanov, “Fuel fabrication and reprocessing for nuclear fuel cycle with inherent safety demands,” Radiochim. Acta, 103, No. 3, 163–173 (2015).
A. Yu. Shadrin, K. N. Dvoeglazov, and Yu. S. Mochalov, “Hydrometallurgical and combined technologies fast reactor MNUP and MOX UNF reprocessing,” J. Phys. Conf. Ser., 1475, 012021 (2020).
E. O. Adamov, A. V. Kashcheev, and Yu. S. Mochalov, “Reprocessing of spent nuclear fuel and recycling of nuclear materials in a two-component nuclear energy,” At. Energiya, 130, No. 1, 28–34 (2021).
A. Shadrin, Yu. Mochalov, K. Dvoeglazov, and V. Kascheev, “Reprocessing of fast reactors mixed U–Pu used nuclear fuel in Russian Federation. Studies and industrial test,” in: Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Ekaterinburg (2017), Paper IAEACN245-76.
V. M. Gelis, O. V. Kharitonov, and L. A. Firsova, “Isolation and purifi cation of americium and curium from solutions after processing SNF RBN by means of displacement complexing chromatography,” Vopr. Rad. Bezopasn., 71, No. 3, 65–71 (2013).
V. Milutin, O. Kharitonov, and L. Firsova, “Hot test of technique separation of americium and curium,” in: Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Ekaterinburg (2017), Paper IAEA-CN245-237.
Author information
Authors and Affiliations
Corresponding author
Additional information
Translated from Atomnaya Énergiya, Vol. 133, No. 1, pp. 34–41, July, 2022.
Rights and permissions
Springer Nature or its licensor (e.g. a society or other partner) holds exclusive rights to this article under a publishing agreement with the author(s) or other rightsholder(s); author self-archiving of the accepted manuscript version of this article is solely governed by the terms of such publishing agreement and applicable law.
About this article
Cite this article
Khomyakov, Y., Mochalov, Y., Zherebtsov, A.A. et al. Technologies of Np, Am Afterburning in Fast Reactors with Mixed Uranium-Plutonium Nitride Fuel. At Energy 133, 35–42 (2022). https://doi.org/10.1007/s10512-023-00969-6
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-023-00969-6