1. Andreeva-Andrievskaya L.N., Nechaeva O.A., Salatov A.V., Sokolov N.B. RAPTA-5: Programme of Design Modelling Bahaviour of Water Cooled Power Reactors and Design Basis Accident Conditions. SSTC NRS, certification sheet №60 of 17.10.96.
2. Bibilashvili Yu.K., Sokolov N.B., Andreeva-Andrievskaya L.N., Tonkov V.Yu., Salatov A.V., Morosov A.M., Smirnov V.P. The oxidized Zr1%Nb VVER-type fuel rod claddings heat resistance during quenching in loss of the coolant accident conditions. 6th International QUENCH Workshop, Forschungszentrum Karlsruhe, October 10-12, 2000.
3. Bibilashvily Yu.K., Sokolov N.B., Salatov A.V., Andreyeva-Andrievskaya L.N., Nechaeva O.A., Vlasov F.Yu. RAPTA-5 Code: Modelling of Behaviour of Fuel Elements of VVER Type in Design Accidents. Verification Calculations. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, on 9-13 October 1995. IAEA-TECDOC-921, Vienna, 1996, pp. 139-152.
4. Thermophysical properties of uranium dioxide;Fink;J. Nucl. Mater.,1981
5. Plastic strain correction in fatigue analysis of nuclear power plant equipment;Fu;Strength Mater.,2021