1. M. Brumovský, “WWER RPV Surveillance Programs,” in International Review of Nuclear Reactor Pressure Vessel Surveillance Programs, ed. W. L. Server and M. Brumovský (West Conshohocken, PA: ASTM International, 2018), 307–346, https://doi.org/10.1520/STP160320170013
2. Standards for Strength Calculation of Elements of Reactors, Steam Generators, Vessels and Piping in Nuclear Power Plants, Prototype and Research Reactors and Stations (in Russian) (Moscow, Russia: Metallurgia, 1973).
3. Standards for Strength Calculations of Components and Piping in NPPs (in Russian), PNAE G-7-002-86 (Moscow, Russia: Energoatomizdat, 1989).
4. Guidelines for Prediction of Radiation Embrittlement of Operating WWER-440 Reactor Pressure Vessels, IAEA-TECDOC-1442 (Vienna, Austria: IAEA, 2004).
5. VERLIFE–Unified Procedure for Assessment of Lifetime of Components and Piping in WWER NPPs during Operation (Brussels, Belgium: European Union, 2008).