Abstract
The paper considers the possibility of replacing container fuel elements of thermal reactors with uranium dioxide or mixed oxide uranium-plutonium fuel with dispersion fuel elements of high uranium density, based on a metal fuel with a matrix of zirconium alloys, demonstrated high radiation resistance in reactor tests. Such fuel can ensure an increase in the duration of a fuel element campaign and/or a decrease in enrichment, which will save natural uranium and increase the breeding ratio. In addition, the content of plutonium in the fuel element will increase by more than 2 times, which can greatly simplify the closure of the fuel cycle. The use of dispersion composite fuel for thermal and fast reactors can replace the currently existing approach, based on the use of uranium dioxide or mixed oxide uranium-plutonium fuel pellets.
Similar content being viewed by others
References
Savchenko, A.M., Vatulin, A.V., Konovalov, I.I.: Fuel of novel generation for PWR and as an alternative to MOX fuel. J. Energy Convers. Manag. 51, 1826–1833 (2010)
Savchenko, A.M., Vatulin, A.V., Kulakov, G.V.: Peculiarities of fuel cycle with advanced composite fuel for thermal reactors. Prog. Nucl. Energy 72, 119–125 (2014)
Savchenko, A.M., Yu, V.: Konovalov, G.V. Kulakov et al., “A new METMET fuel element concept for using in floating power units and small nuclear power plants,” Voprosy Atomnoi Nauki i Tekhniki. Ser. Materialovedenie i Novye Materialy [In Russian. Iss. 4(110), 51–64 (2021)
Samoilov, A.G., Volkov, V.S., Solonin, M.I.: Fuel elements of Nuclear Reactors [In Russian. Energoatomizdat, Moscow (1996)
A.M. Savchenko, “The issue of novel trends in fuel alloying to reduce interaction,” Proc. of the Research Reactor Fuel Management (RRFM-2018) Conf. Germany, paper A0147 (2018).
A.M. Savchenko, Yu.V. Konovalov, A.V. Laushkin et al., “Zirconium matrix alloys for dispersion fuel compositions of high uranium density,” Atomnaya Energiya [In Russian], 122, Iss. 6, 349–352 (2017).
Degueldre, C., Paratte, J.: Concepts for an inert matrix fuel, an overview. J. Nucl. Mater. 274, 1–6 (1999)
Oversby, V., McPheeters, C., Degueldre, C.: Control of civilian plutonium inventories using burning in a nonfertile fuel. Ibid 245, 112 (1997)
Porta, J., Doriath, J.-Y.: Toward very high burnups, a strategy for plutonium utilization in pressurized water reactors. J. Nucl. Mater. 274, 153 (1999)
Schram, R., Laan, R., Klaassen, F.: The fabrication and irradiation of plutonium-containing inert matrix fuels for the “Once Though Then Out” experiment. J. Nucl. Mater. 319, 118 (2003)
Lipkina, K., Savchenko, A., Skupov, M.M.: Metallic inert matrix fuel concept for minor actinides incineration to achieve ultra-high burn-up. J. Nucl. Mater. 452, 348–351 (2014)
Lee, T.: Technological change of nuclear fuel cycle in Korea: the case of DUPIC. Prog. Nucl. Energy 45, 85–102 (2004)
Author information
Authors and Affiliations
Corresponding author
Additional information
Translated from Atomnaya Energiya, Vol. 134, No. 3–4, pp. 147–153, March–April, 2023.
Publisher’s Note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
Original article submitted July 14, 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
Savchenko, A.M., Karpyuk, L.A., Dergunova, E.A. et al. Fuel cycles with advanced dispersion fuel elements of high uranium density. At Energy 134, 181–189 (2023). https://doi.org/10.1007/s10512-024-01041-7
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-024-01041-7