1. V. P. Denisov and Yu. G. Dragunov, WWER Reactor Plants for Nuclear Power Stations [in Russian], IzdAT, Moscow (2002).
2. N. V. Sharyi, V. P. Semishkin, V. A. Piminov, and Yu. G. Dragunov, Strength of the Basic Equipment and Pipelines of WWER Reactor Plants [in Russian], IzdAT, Moscow (2004).
3. V. V. Kharchenko and A. Yu. Chirkov, “Some aspects of inclusion of loading history in the fracture strength analysis of reactor pressure vessels under thermal shock conditions,” Strength Mater., 48, No. 5, 603–609 (2016).
4. V. V. Kharchenko, V. A. Piminov, A. Yu. Chirkov, et al., “Elastoplastic fracture resistance analysis of NPP primary circuit equipment elements,” Strength Mater., 45, No. 4, 397–405 (2013).
5. I. F. Akbashev, Yu. M. Maksimov, V. A. Piminov, and B. Z. Margolin, “The main results of the evaluation of new approaches to determining the life of WWER reactor vessels,” in: Materials Science Problems in the Design, Manufacture, and Operation of NPP Equipment [in Russian], St. Petersburg (2002), pp. 6–11.