[1]
D.E. Burkes, C.A. Papesch, A.P. Maddison, T. Hartmann, F.J. Rice, Thermophysical properties of DU-10wt. % Mo alloys, Journal of Nuclear Materials, 403 (2010) 160-166.
DOI: 10.1016/j.jnucmat.2010.06.018
Google Scholar
[2]
Fink J.K. Thermophysical properties of uranium dioxide. Journal of Nuclear Materials, 2000, 279, 1-18.
Google Scholar
[3]
S. Kaity, J. Banerjee, M.R. Nair, K. Ravi, S. Dash, T.R. Kutty, A. Kumar, R.P. Singh, Microstructural and thermophysical properties of U–6 wt. % Zr alloy for fast reactor application, Journal of Nuclear Materials. 427 (2012) 1-11.
DOI: 10.1016/j.jnucmat.2012.03.045
Google Scholar
[4]
M. Skakov, N. Mukhamedov, W. Wieleba, I. Deryavko, Study of corium thermophysical properties of light water reactor with different oxidation degrees of zirconium. Research Journal of Pharmaceutical, Biological and Chemical Sciences, 7(4) (2016).
Google Scholar
[5]
М. Skakov, A. Vurim, N. Mukhamedov, E. Batyrbekov, A. Pakhnits, V. Vityuk, S. Khametov, I. Deryavko, Innovative patent of RK, 30988 (2016).
Google Scholar
[6]
V. Zhdanov, V. Baklanov, The Methodology of Determining Heat-Transfer Properties of the Samples of Promising Fuel for Water-Moderated Water-Cooled Power Reactor, Nuclear Power of the Republic of Kazakhstan, Kurchatov, 2009, pp.150-156.
Google Scholar