DEVICE FOR INSTALLATION OF THE OUTER HEAT INSULATION OF A NUCLEAR REACTOR VESSEL

The invention relates to the field of nuclear engineering, and more particularly to auxiliary devices for nuclear power plants, and even more particularly to devices for installing external thermal insulation on a nuclear reactor vessel, and can be used in nuclear power stations for performing recovery annealing operations on weld seams of pressurized water reactor vessels. The claimed invention is directed toward solving the problem of allowing the installation and removal of thermal insulation on the outer surface of a pressurized water reactor vessel from the confined space below a reactor and at elevated levels of ionizing radiation. The technical result of the present invention is that of reducing the temperature gradient across the thickness of a nuclear reactor vessel by thermally insulating the outer surface of the reactor vessel, providing for uniformity of the physical properties of the metal and weld seams of the reactor vessel, and reducing the impact of thermal effects on surrounding structures during the recovery annealing of weld seams and (or) of the main metal of a pressurized water reactor vessel. The technical result is achieved in that a device for installing external thermal insulation on a nuclear reactor vessel comprises a mobile transport trolley equipped with a mechanism for the movement thereof, a detachable carrier rim disposed on the transport trolley and to which thermal insulation for the reactor vessel is attached, and at least two hoists disposed on opposite sides of the reactor vessel at the level of the top of the reactor vessel, the detachable carrier rim being connected to the hoists to allow raising and lowering of the rim. Use of the claimed invention makes it possible to install and remove thermal insulation on the outer surface of a pressurized water reactor vessel from the confined space below a reactor and at elevated levels of ionizing radiation. The thermal insulation of the outer surface of a reactor vessel makes it possible to reduce the temperature gradient across the thickness of the nuclear reactor vessel, provide for uniformity of the physical properties of the metal and weld seams of the reactor vessel, and reduce the impact of thermal effects on surrounding structures during the recovery annealing of weld seams and (or) of the main metal of a pressurized water reactor vessel. L'invention se rapport au domaine de l'énergie atomique, concerne notamment des dispositifs auxiliaires pour des installations nucl