2011, Хомяков, О. В., Хомяков, Олег Владимирович, Девятко, Ю. Н.

2019, Devyatko, Yury N., Khomyakov, Oleg V., Tenishev, Andrey V., Mikhalchik, Vladimir V., Shornikov, Dmitry P., Хомяков, Олег Владимирович, Тенишев, Андрей Вадимович, Михальчик, Владимир Валерьевич, Шорников, Дмитрий Павлович

The paper proposes a method for reducing the true pore size in oxide nuclear fuel using a well-known histogram for the distribution of the pores cross sections across the polished section. It is shown that the problem of constructing a continuous pore size distribution function from the pore size distribution histogram is incorrect. Histograms showing pore distributions across the polished sections of oxide nuclear fuel sintered under various conditions are obtained. The Scheil-Saltykov method was used to reduce histograms for 3D pore size distributions in uranium oxide fuel.

2019, Девятк, Ю. Н., Новиков, В. В., Хомяков, О. В., Новиков, Владимир Владимирович, Хомяков, Олег Владимирович

A model of radiation-induced densification of uranium-gadolinium fuel was developed. The fuel is established to be in the brittle state in the volume of uranium-gadolinium fuel pellet containing a burnable neutron absorber under irradiation and in the plastic state out of this volume. The relative change in a pellet volume for uranium-gadolinium fuel is shown to be lower than that for uranium oxide nuclear fuel with the same microstructure.

2017, Девятко, Ю. Н., Новиков, В. В., Хомяков, О. В., Хомяков, Олег Владимирович

Formation mechanism of massive hydrides in irradiated zirconium cladding is established. It is shown that the duration of formation process is defined by a period of time up to destruction of oxide film on the internal surface of fuel cladding. The time required for massive hydride to grow through the thickness of zirconium cladding is established.

2019, Ivanov, B. V., Anikin, A. S., Bukin, A. N., Sergeecheva, Y. V., Devyatko, Y. N., Khomyakov, O. V., Хомяков, Олег Владимирович

© 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.