Персона: Хомяков, Олег Владимирович
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The Mechanism of Swelling of Irradiated Oxide Nuclear Fuel: Part II. Swelling during Power Ramps
Identification of the sintering mechanism of oxide nuclear fuel through the analysis of experimental pore size distributions
© 2020 The Physical Society of Japan.The paper studies the sintering kinetics of pelletized oxide nuclear fuel in terms of various parameters (heating rate, sintering temperature, partial pressure of oxygen in sintering atmosphere). It considers calculated experimental pore size distributions in sintered fuel pellets. Study of the evolution of pore size distributions let us determined the physical mechanism of sintering of uranium dioxide. The sintering process is controlled by the mechanism of viscous flow under the influence of capillary forces and residual stresses.
А MODEL OF RADIATION-INDUCED DENSIFICATION OF OXIDE NUCLEAR FUEL
А process of radiation-induced densification of UO2 is analyzed. It is shown that in vicinity of fission fragment tracks the local melting area and zone of plastic yield are formed. It is developed model of closing of pore in the plastic medium due to influence of stress created in fission fragment tracks.
Measurement of Hydrogen Diffusion in Zirconium Alloys by the Radioluminography Method
© 2019, Pleiades Publishing, Ltd.Abstract: A method for obtaining the quasi-one-dimensional distribution of tritium in zirconium alloys was developed. Various conditions of saturation of samples with tritium were analyzed and distributions of tritium concentration corresponding to the saturation conditions were measured. An algorithm for restoring of the diffusion coefficient of hydrogen in zirconium alloys by the radioluminography method was developed. The temperature dependence of the hydrogen diffusion in E110 alloy was constructed.