One possible use for the wastes from nuclear power production is burning the secondary fuel (actinides) produced and transmutation of long-lived fission products into short-lived and stable isotopes which can then be reliably stored [1]. A fuel cycle with a mobile carrier of nuclear fuel in electronuclear setups becomes important in this connection. One possible aggregate state of liquid nuclear fuel is a suspension based on a mixture of oxides of plutonium and actinides. Although the technology for chemical reprocessing of fuel in water media using this cycle is generally well known, certain thermophysical and rheological parameters need to be determined more accurately. These include the dynamic viscosity, the thermal conductivity, the specific heat, the enthalpy of suspensions in the temperature range 200-300°C, and the concentration 30-125 g/dm 3 .The calculations are based on the simplest physical models which neglect surface phenomena. They are performed with certain assumptions which reduce mainly to the following: the suspension particles are spherical and about 30 µm in diameter, they all have the same size, the average initial body density of the particles is 11.4 g/cm 3 (the density of plutonium dioxide) [1, 2], the particles are uniformly distributed in the dispersing medium (heavy water), and the fragmentation to a colloidal state under irradiation (neutron fluence ~10 22 cm -2 ) with a 16-day cycle for reprocessing fuel from an electronuclear system will not exceed 10% of the total number of particles [3,4].Viscosity. The viscosity was calculated using Einstein's equation, written for convenience in the form enthalpy of the mass fraction of heavy water and when the concentration of the plutonium, Np, Am, and Cm changes from 125 to 31 g/dm 3 they decrease by not more than 15 and 5%, respectively, of the specific heat and enthalpy of heavy water.
The results of an assessment of the influence of purging on the 3 He and, correspondingly, tritium concentrations in heavy-water coolant (moderator) need, in our opinion, a more detailed analysis. * As shown in a previous publication, if all helium in heavy water is conserved, then the solution of the system of two linear equations describing the accumulation of tritium under reactor conditions has the form 2 1 of purging on the tritium concentration in the heavy water coolant of a nuclear reactor," At. Énerg., 97, No. 2, 159-160 (2004).
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