1. Y. G. Dragunov, A. A. Petrov, A. V. Ivanov, et al., “Modernization and life extension of power with RBMK,” At. Energ., 113, No. 1, 6–13 (2012).
2. A. S. Zaimovskii, A. V. Nikulin, and N. G. Reshetnikov, Zirconium Alloys in Nuclear Power, Energoatomizdat, Moscow (1994).
3. S. V. Pavlov, A. V. Sukhikh, and S. S. Sagalov, Eddy Current Testing Methods in Reactor Materials Science, NIIAR, Dimitrovgrad (2010).
4. A. N. Kostyuchenko, “Distribution of the oxide film on the outer surface of the cylindrical elements of spent FA in VVER and RBMK,” At. Energ., 102, No. 6, 383–385 (2007).
5. A. N. Kostyuchenko, V. V. Chesanov, E. A. Zvir, et al., “Oxidation of fuel element cladding in RBMK-1000 during normal operation,” in: 9th Russ. Conf. on Reactor Materials Science, Dimitrovgrad, Sept. 14–18, 2009, pp. 664–669.