Abstract: The invention relates to the field of nuclear technologies, in particular to an oxide-based uranium-plutonium nuclear fuel for an atomic power station with thermal neutron reactors. The technical result of the invention is the development of a REMIX-type fuel composition formulation making it possible, in the nuclear fuel cycle, to involve fissile nuclear materials regenerated from spent nuclear fuel with the simultaneous use of enriched natural uranium, and also moreover providing a solution to the problems of separately using previously isolated plutonium (including weapons-grade plutonium), of reducing the quantity of spent nuclear fuel by recycling fissile materials from spent nuclear fuel during the lifespan of a nuclear reactor (up to 5 recyclings), of economizing on natural uranium for manufacturing fuel and, as a result, of making the nuclear fuel cycle self-sustainable.

Abstract: Evaporators used in radiochemical production designed to evaporate highly active solutions and devices designed to create thin film in the heating chambers. The film former contains a liner in the upper part of the heat exchange tube attached to the spindle of the bellows assembly of the evaporator lid. The liner is provided with a radiation-proof tip that is not wettable by liquid being evaporated. The tip is made of two conjugate cones: the upper back cone and lower right cone, with the lower cone having a cylindrical belt with protrusions on it designed to center the conical tip on the inner surface of the heat exchange tube. A cap is mounted movably on the liner, with grooves on the lower end of the cap along the entire perimeter. The liner attached to the spindle is connected by fins with adjacent liners installed in heat exchange tubes.

Abstract: Evaporators used in radiochemical production designed to evaporate highly active solutions and devices designed to create thin film in the heating chambers. The film former contains a liner in the upper part of the heat exchange tube attached to the spindle of the bellows assembly of the evaporator lid. The liner is provided with a radiation-proof tip that is not wettable by liquid being evaporated. The tip is made of two conjugate cones: the upper back cone and lower right cone, with the lower cone having a cylindrical belt with protrusions on it designed to center the conical tip on the inner surface of the heat exchange tube. A cap is mounted movably on the liner, with grooves on the lower end of the cap along the entire perimeter. The liner attached to the spindle is connected by fins with adjacent liners installed in heat exchange tubes.

Abstract: Power sources based on semiconductor converters using the beta-voltaic effect. The Beta-voltaic battery comprises housing and cover, semiconductor converters, insulating and radioisotope elements and conductive contacts configured to make one or several packs connected in parallel and (or) in series. The pack is assembled from converters, whose opposite-polar surfaces face each other, with conductive radioisotope elements placed between them. The packs are separated by insulating elements, along the perimeter of which grooves are evenly spaced. The opposite grooves have conductive contacts designed in such a way as to electrical connect to both the conductive contacts of the extreme semiconductor converters of each pack and the controller. Highly enriched Nickel-63 is used as a radioisotope element, which is deposited on n-layers of semiconductor converters.

Abstract: The method concerns processing irradiated (spent) nuclear fuel (SNF), it is primarily aimed at isolating and trapping tritium, and can be used in nuclear power industry for treating SNF. This method provides for a two-phase voloxidation of a reaction mass using gas-air mixture, the reaction mass including fragmented uranium dioxide SNF elements with containers. The first phase is carried out at 400-650° C. in the presence of air and additional carbon dioxide. The second phase is carried out at 350-450° C. using a stream of an air-vapor mixture that can be oxygen-enriched. Both phases are carried out with a repeated mechanical activation of the reaction mass. Provided in the course of the voloxidation is the gas replacement at the hour rate of about 10-50 fold the reaction chamber gas volume. Before being introduced into the reaction chamber, the gas is preheated up to the chamber internal temperature.

Abstract: The method concerns processing irradiated (spent) nuclear fuel (SNF), it is primarily aimed at isolating and trapping tritium, and can be used in nuclear power industry for treating SNF. This method provides for a two-phase voloxidation of a reaction mass using gas-air mixture, the reaction mass including fragmented uranium dioxide SNF elements with containers. The first phase is carried out at 400÷650° C. in the presence of air and additional carbon dioxide. The second phase is carried out at 350÷450° C. using a stream of an air-vapor mixture that can be oxygen-enriched. Both phases are carried out with a repeated mechanical activation of the reaction mass. Provided in the course of the voloxidation is the gas replacement at the hour rate of about 10÷50-fold the reaction chamber gas volume. Before being introduced into the reaction chamber, the gas is preheated up to the chamber internal temperature.