Groups of materials are compared according to their possible use for fuel-pin cladding in the development of accident-tolerant fuel (ATF). Ferritic, ferritic-martensitic, and austenitic steels and chromium-nickel alloys are studied. Currently, only the chromium-nickel alloy 42KhNM can be used in VVER under normal operating conditions as cladding material for ATF. Pre-reactor and reactor studies are required in order to assess the possibility of using for this purpose the other materials which are under consideration.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
A. A. Nikitina, V. S. Ageev, M. V. Leontyeva-Smirnova, et al., “Development of work on structural materials for fast-reactor cores” At. Energ., 119, No. 5, 292–300 (2015).
A. Savchenko, V. Ivanov, V. Novikov, et al., “Review of A. A. Bochvar Institute activities in developing potentially accident-tolerant fuel for light-water reactors,” in: Proc. TopFuel-2015 Conf., Zurich, Switzerland, Sept. 13– 18, 2015, pp. 21–30.
K. Terrani, “Accident-tolerant fuel cladding development: promise, status, and challenges,” J. Nucl. Mater., 501, 13–30 (2018).
M. I. Solonin, V. P. Kondrat’ev, S. N. Votinov, et al., “Alloy KhNM-1 as a promising material for structural elements of nuclear and thermonuclear reactors with water coolant,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater., No. 1 (52), 13–20 (1995).
M. I. Solonin, V. P. Kondrat’ev, V. N. Rechitsky, et al., “XHM-1 alloy as a promising structural material for water-cooled fusion reactor components,” J. Nucl. Mater., 233–237, 586–591 (1996).
M. I. Solonin, V. P. Kondrat’ev, V. N. Rechitsky, et al., “Cr–Ni alloys for fusion reactors,” J. Nucl. Mater., 258–263, 1762–1766 (1998).
A. V. Vatulin, V. P. Kondratyev, V. N. Rechitsky, et al., “Research of corrosion and radiation resistance of nickel-chromium alloy Bochvaloi,” Metalloved. Term. Obrab. Met., No. 11, 19–24 (2004).
G. V. Kulakov, S. A. Ershov, Yu. V. Konovalov, et al., “The main properties of the 42KhNM alloy and the prospects for its implementation as a structural material for VVER elements,” Abstr. 9th Conf. on Reactor Materials Science, SSC RIAR, Dimitrovgrad, May 27–31, 2019, pp. 37–39.
I. F. Gilmutdinov, V. Yu. Shishin, F. N. Kryukov, et al., “Radiation resistance of experimental fuel elements with uranium dioxide-silumin dispersion fuel composition for the modernized core of the SM reactor,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater, No. 4 (91), 124–133 (2017).
I. F. Gilmutdinov, V. Yu. Shishin, F. N. Kryukov, et al., “Swelling of uranium dioxide-silumin dispersion fuel composition in experimental fuel elements of the SM reactor,” At. Energ., 124, No. 1, 23–29 (2018).
A. V. Salatov, A. V. Kumachev, O. A. Nechaeva, et al., “Experimental and computational studies of the behavior of VVER fuel elements under LOCA conditions (experiment MIR-LOCA/60),” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater., No. 1 (74), 26–38 (2013).
P. P. Grinchuk, V. N. Golovanov, M. I. Solonin, et al., “Radiation and corrosion resistance of the KhNM-1 alloy,” Vopr. At. Nauki Tekhn. Ser. Materialoved. Nov. Mater., No. 1 (64), 273–280 (2005).
Author information
Authors and Affiliations
Corresponding author
Additional information
Translated from Atomnaya Énergiya, Vol. 128, No. 4, pp, 203–208, April, 2020.
Rights and permissions
About this article
Cite this article
Karpyuk, L.A., Savchenko, A.M., Leont’eva-Smirnova, M.V. et al. Steel Cladding for VVER Fuel Pins in the Context of Accident-Tolerant Fuel: Prospects. At Energy 128, 218–222 (2020). https://doi.org/10.1007/s10512-020-00679-3
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-020-00679-3