The results of physical-metallurgical studies of fuel-element cladding in a nuclear power plant with a boiling-water vessel reactor are presented. It is shown that the fuel materials are highly reliable under the operating conditions.
Similar content being viewed by others
References
V. A. Tsykanov, V. K. Shamardin, A. B. Andreeva, et al., “Physical-metallurgical studies of VK-50 reactor fuel assemblies,” At. Énerg., 56, No. 3, 131–134 (1984).
I. M. Smirnov, Distribution of the Elements in Deposits on the Cladding of Fuel Elements in Water-Cooled Nuclear Reactors: Auth. Abstr. Cand. Dissert. Techn. Sci., Ulyanovsk (2011).
A. M. Krasnov, V. M. Eshcherkin, V. E. Shmelev, et al., “Processes leading to the concentration of dissolved impurities in coolant (‘hide-out’) on the VK-50 research reactor,” Teploenergetika, No. 7, 18–23 (2002).
V. V. Konyashov and A. M. Krasnov, “Experience in operating the VK-50 nuclear reactor with non-hermetic fuel elements,” in: Trudy GNTs RF NIIAR, Dimitrovgrad (2000), Iss. 3, pp. 25–26.
A. Garlick. R. Sumerling, and G. Shires, “Crud-induced overheating defects in water reactor fuel pins,” J. Brit. Nucl. Energy Soc., 16, No. 1, 77–80 (1977).
J. Moon, “A metallographic examination of general white spottiny in oxide films on zircaloy-2,” Corros. Sci., 8, 109–110 (1968).
K. N. Brusov, P. G. Krutikov, Z. S. Osminin, et al., Products of Corrosion in the Loops of Nuclear Power Plants, Energoatomizdat, Moscow (1989).
L. N. Rozhdestvenskaya, A. I. Zabelin, Yu. V. Chechetkin, et al., “Distribution of deposits and activity on the surfaces of equipment and piping in a single-loop VK-50 reactor,” At. Énerg., 30, No. 2, 122–126 (1971).
A. I. Zabelin, Study of the Water-Chemistry Regimes of Nuclear Power Plants with a VK-50 Reactor, Preprint NIIAR-23(528), Dimitrovgrad (1982).
A. S. Kurskiy and G. V. Filiakin, “Corrosion cracking of KH18N10T steel in during prolonged operation in the VK-50 boiling-water reactor,” in: Int. Conf. Materials Engineering Problems During Design, Fabrication and Operation of Equipment in a Nuclear Power Plant, St. Petersburg (2008), pp. 208–215.
V. A. Tsykanov, Yu. V. Chechetkin, V. E. Shmelev, et al., “Study validating the possibility of using a boiling-water reactor for a nuclear heat-generating plant,” Prospects for Using Nuclear Reactors for Supplying Heat to Cities and Industrial Enterprises, Dimitrovgrad (1978), pp. 94–107.
I. M. Smirnov, “Method of analytical monitoring of surface deposits on the cladding of fuel elements of water-cooled nuclear reactors,” Zavod. Lab.. Diagn. Mater., 75, No. 11, 3–7 (2009).
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya,Vol. 115, No. 2, pp. 82–87, August, 2013.
Rights and permissions
About this article
Cite this article
Kurskiy, A.S., Smirnova, I.M., Filiakin, G.V. et al. Serviceability of the Fuel Elements in a VK-50 Boiling-Water Vessel Reactor. At Energy 115, 95–101 (2013). https://doi.org/10.1007/s10512-013-9755-2
Received:
Revised:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-013-9755-2