摘要:
The invention relates to nuclear power engineering and can be used in power plants with lead-containing liquid metal coolants, and particularly in fast neutron reactors. The proposed nuclear reactor and the method and system for monitoring the thermodynamic activity of oxygen in a coolant with continuously operational oxygen thermodynamic activity sensors located in the "hot" and "cold" zones of the reactor vessel and an additional intermittently operational sensor make it possible to carry out continuous monitoring in order to maintain set oxygen thermodynamic activity values in a liquid metal coolant under any prescribed operating regime.
摘要:
The invention relates to energy mechanical engineering and can be used in power installations involving a liquid-metal heat carrier. A mass transfer apparatus including a housing and, provided therein, a flow reaction chamber filled with a solid-phase granulated oxidation agent, and an electric heater positioned in the reaction chamber. The housing of the apparatus is equipped with a repository for reserves of the solid-state granulated oxidation agent, said repository being located below the reaction chamber and being made in the form of a cup having a bottom, said cup being connected to the reaction chamber. The technical result consists in extending the operational duration of the mass transfer apparatus.
摘要:
The method of the long-term storage of waste nuclear fuel of a nuclear reactor consists in that, first, prior to the waste fuel assembly of the nuclear reactor being disposed in a steel case and latter being hermetically sealed with a cover, a material which is chemically inert in relation to the material of the casing of the fuel elements of the waste fuel assemblies, to the material of the body of the case, to air and to water, is arranged in the steel case, the steel case is mounted in a heating device, the steel case is heated along with the material arranged in said steel case until said material passes into a liquid state, and then the waste fuel assembly which has been extracted from the nuclear reactor is arranged in the steel case in such a way that the fuel pat of the fuel elements of the waste fuel assemblies is lower than the level of the liquid material in steel case, the waste fuel assembly is fixed in this position, and the case is hermetically sealed the cover, whereupon the hermetically sealed case is extracted from the heating device and mounted in a storage facility which is cooled by atmospheric air. This technical solution makes it possible to ensure long-term safe storage of waste fuel assemblies of a nuclear reactor in storage facilities with cooling using atmospheric air, in particular with natural circulation of atmospheric air, and also to transport the waste of the fuel assemblies to a factory for processing so as to ensure an increased level of safety.
摘要:
The invention relates to nuclear technology, and specifically to systems for controlling and protecting nuclear reactors. A drive of an emergency safety rod of a nuclear reactor includes an electric drive, a reduction gear, and a rack-and-pinion gear. The electric drive contains a contactless electric motor based on permanent magnets, which is installed in the housing of the electric drive with a motor rotor position sensor, and a reduction gear for changing the rate of rotation of the electric drive. A toothed rack is installed along the axis of the rack-and-pinion gear in order to provide for the reciprocating motion of a system absorber rod connected thereto. A toothed electromagnetic clutch having a contactless current supply is installed on an inner shaft of the rack-and-pinion gear, enabling the rigid and simultaneous mechanical coupling of half-couplings, and the drive contains a reverse motion coupling, a rack-separation spring and toothed rack position sensors. The invention makes it possible to reduce the time necessary for adding negative reactivity to a nuclear reactor core.
摘要:
The invention relates to energy mechanical engineering and can be used in power installations involving a liquid-metal heat carrier. A mass transfer apparatus including a housing and, provided therein, a flow reaction chamber filled with a solid-phase granulated oxidation agent, and an electric heater positioned in the reaction chamber. The housing of the apparatus is equipped with a repository for reserves of the solid-state granulated oxidation agent, said repository being located below the reaction chamber and being made in the form of a cup having a bottom, said cup being connected to the reaction chamber. The technical result consists in extending the operational duration of the mass transfer apparatus.
摘要:
The present nuclear reactor with a liquid metal coolant comprises a housing (1) having a separating shell (6) disposed therein. In the annular space (5) between the housing and the separating shell are disposed at least one steam generator (3) and at least one pump (4). Inside the separating shell (6) there is an active region (2), above which a heat collector (8) is disposed which is in communication with the vertically central portion of the steam generator (3) in order to separate a stream of liquid metal coolant into ascending and descending flows, or the heat collector (8) is in communication with the upper portion of the steam generator in order to create a counter-flow heat exchange regime. Below the reactor head is an upper horizontal cold collector (10) with an unfilled level of coolant, and below the steam generator (3) is a lower accumulating collector (11) in communication with the upper cold collector (10). The inlet of the pump (4) is connected to the upper cold collector (10), and the outlet of the pump (4) is connected to a lower annular pressure collector (12), wherein collectors (11) and (12) are separated by a horizontal partition (13), and collector (12) is in communication with a distributing collector (15) of the active region.
摘要:
This invention relates to nuclear power engineering and may be used in power plants with liquid metal lead containing coolants, particularly in fast neutron reactors. The invention helps improve the safety of nuclear power plants. For this purpose, a nuclear power plant is proposed comprising: a reactor vessel with central and peripheral sections; a reactor cavity with a core located in the central part of the vessel; liquid metal coolant, at least one circulation pump for circulating the liquid metal coolant and at least one steam generator, located in the peripheral section of the vessel; a cavity with shielding gas located above the coolant; at least one shielding gas dispenser located in the peripheral section of the vessel, above the top cut of the steam generator in the suction area of the circulating pump comprising an intake and working sections, with the intake section located in the shielding gas cavity and having openings in its upper part, and the working section located under the free level of the liquid metal coolant.
摘要:
The invention relates to electrical engineering namely to sealed inputs of electric circuits into the confinement area of multi-layer nuclear power plant containment. The development can be used in penetrations through external and internal walls subjected to relative mutual displacement due to seismic events or thermal expansion of walls and penetrations. The purpose of this invention is to improve operating reliability of the sealed cable input if hard-bending high-voltage electrical conductors are used. This purpose is achieved by the sealed cable input through external and internal walls of the nuclear power plant containment containing an embedded connection pipe 3 inside internal wall 1 with internally and rigidly fixed cable 2 input 44. Compensation means for relative motion of cable 2 and external wall 11 are located in line with connection pipe 3 inside external wall 11. Compensation means are equipped with pipe 19 with bellows 24 on external end 20 and the second similar bellows 25 located symmetrically on the opposite end 21 of pipe 19 near internal surface 18 of external wall 11. Loose ends 30 and 31 of both bellows 24 and 25 are tapered, their internal surfaces 28 and 29 are supporting cable 2 output 46 freely installed in pipe 19 with gap 47 in relation to internal surface 49 of pipe 19. Gap 47 between braiding 48 over the external surface of cable 2 and internal surface 49 of pipe 19 is selected based on the calculations. Gap 47 shall be at least equal to the maximum orthographic thermal and seismic planar motion of internal wall 1 in relation to external wall 11 and the change of cable 2 coaxial position in pipe 19. 1 independent claim, 5 dependent claims, 3 figures.
摘要:
A method for the innercontour passivation of steel surfaces of a nuclear reactor consists in filling a first contour of a nuclear reactor with a liquid metal coolant, introducing a reagent into the liquid metal coolant, said reagent interacting with the material of elements of the first contour, forming a protective film, and heating the liquid metal coolant, having the reagent introduced therein, to a temperature allowing for conditions for forming the protective film. The liquid metal coolant having the reagent introduced therein is kept at said temperature until a continuous protective film is formed on the surface of the material of the elements of the first contour. The liquid metal coolant having reagent introduced therein is heated by means of the friction thereof against rotating vanes of a vane pump, which is submerged in the liquid metal coolant. The present invention thus provides for a simpler passivation process, a more reliable passivation mode, an increase in the safety thereof and a simpler control over the process of passivation of steel surfaces.
摘要:
Disclosed is a hydrogen igniter for igniting hydrogen contained in a gaseous medium, said hydrogen igniter comprising a housing with openings for the supply and discharge of a gaseous medium, and a filler in the form of bismuth oxide and/or lead oxide, disposed inside the housing. Also disclosed are a system for purifying a gaseous medium of hydrogen having such a hydrogen igniter, and a method for the repeated use of such a system. The igniter and the system can be used in a nuclear reactor facility