1. Description of Natural Circulation and Passive Safety Systems in Water Cooled Nuclear Power Plants, IAEA Tecdoc-Draft, IAEA, Vienna (2004).
2. A. M. Bakhmetyev, M. A. Bolsukhin, V. A. Babin, et al., “Problems of calculation and experimental validation of SPOT ZO for next-generation NPP,” in: 5th Int. Sci. Techn. Conf. on Safety of NPP with VVER, Podolsk, May 29 – June 1, 2007, OKB Gidropress, Vol. 2, pp. 303–308.
3. V. A. Vasilenko, Y. A. Migrov, V. K. Drought, et al., “The significance and place of the KMS large-scale stand in solving the safety problems of nuclear power plants with VVER,” At. Energ., 115, No. 4, 189–192 (2013).
4. V. V. Bezlepkin, M. A. Zatevakhin, O. P. Kraktunov, et al., “Experimental study of system removing heat from the interior of the containment on SMK,” ibid., 197–201.
5. D. Powers, J. Brockmann, and A. Shiver, Mechanical Model of Radionuclide Release and Aerosol Generation during Core Debris Interactions with Concrete, SAND85-1370, NUREG/CR-4308, Sept. 1985.