RU24748U1 - NUCLEAR POWER PLANT - Google Patents

Description

The solution relates to nuclear engineering and can be used in reactor installations with a liquid metal coolant (LMT).

Known nuclear power plant integrated layout, containing a reactor with a sodium coolant, with an active zone located below the free level of the coolant, steam generators, shkkkulyatsii means and heat exchangers of the emergency heat removal system (see Morgulova T.Kh., Nuclear power plants. - M.: Higher school 1984 p. 251).

The disadvantage of this technical solution is the use of an inert gas (argon) in the cooldown system of the reactor, which has a relatively small heat capacity and cannot provide effective heat removal.

The tasks to be solved are improving the cooldown system and increasing safety by implementing the principle of internal safety of the reactor block (with lead LMC).

The technical result is the use of a mixture of air (atmospheric) and drops of liquid (water) as a cooling medium, which leads to a significant increase in the heat capacity of the heat sink medium, as well as a constructive implementation of the device for forming this two-phase mixture.

The technical result is achieved in that the installation containing the reactor with lead LMW or its alloys, with an active zone located below the free level of the coolant, steam generators, circulation means, a protective gas system, cooldown heat exchangers, characterized in that the cooldown heat exchanger is made in the form of a channel formed by two coaxial pipes, the outer of which is muffled from below at the end section, the channel is buried under the free level of the coolant, at the inlet section device is installed in the liquid droplets enter vozdzosa flow coupled through a valve situated above the water capacity of the device, the input and output ends of channel communicated with the atmosphere.

In FIG. 1 shows a diagram of a nuclear power plant that implements the proposed technical solution. An active zone 3, steam generators 4, circulation means, for example, pumps 5, and cooldown heat exchangers are located in a nuclear reactor 1 with an LMW under a free level 2 of coolant. The heat exchanger of the cooldown system is a channel 6 buried under the free level 2 of the coolant, the end section 7 of which is located at the level of the entrance to the pressure chamber 8 of the reactor core, the outlet end 9 is connected to the atmosphere through an exhaust ventilation system, for example, through an exhaust pipe 10. On the nozzle 12 is connected to the atmosphere inlet section 11, the narrowed part of which is connected through a valve 13c to the water tank 14 located above the nozzle 12.

The operation of the proposed device and, accordingly, heat removal from

the core of the reactor of a nuclear power plant is as follows. Through the cooldown heat exchangers during the operation of a nuclear power plant, the natural circulation of atmospheric air is constantly carried out, removing a small amount of heat. The system is constantly ready for operation. When there is a need for cooling, the valve 13 opens on the water supply line to the device for introducing its drops (spray). Through a nozzle 12 from a water tank 14 by gravity, water droplets are introduced into the air stream, the evaporation of which will occur both on the walls of the channel and in the air stream. Due to the evaporation of water droplets and partial heating of the air, heat will be removed from the channel walls and heat will be removed with the vapor-air mixture removed through an exhaust ventilation system, for example, through an exhaust pipe 10 into the atmosphere. If necessary, it is possible to control the flow rate of water entering the narrowed part of the nozzle 12. The use of this technical solution will allow the following leaner:

to produce effective heat removal from the core of a nuclear power plant with VL / P. The use of water for heat removal (without air) is unacceptable, since the melting temperature of lead is 327 ° C, the boiling point of water at 0.1 MPa is 100 ° C, it is possible to solidify the coolant and the appearance of obstruction in the circulation path. In the reactor, the use of gases (air, nitrogen, etc.) or water vapor (l 4o J

3. ineffective due to the substantially small heat capacity of these

media, the presence of restrictions on their speeds and sizes of the passage sections of the circulation channels;

to ensure constant readiness for operation of the cooling system due to passive means (constant natural air circulation);

- to ensure the cooldown of the reactor of a nuclear power plant with LMW due to passive means of supplying water droplets to the air stream (due to gravity);

to exclude active elements (pumps, etc.) from the composition of the cooling systems, as well as gas cylinders under pressure, from which the loss of working media is possible;

to simplify the system of cooling the reactor.

 ieSiEd

4 FORMULA

Claims (1)

A nuclear power plant containing a reactor with lead coolant or its alloys, with an active zone, steam generators, circulation means, a shielding gas system, cooldown heat exchangers placed under a free coolant level, characterized in that the cooldown heat exchanger is made in the form of a channel formed by two coaxial pipes, the outer of which is muffled from below at the end section, the channel is buried under the free level of the coolant, at the inlet section of the channel A device was introduced for introducing liquid droplets into an air stream connected through a valve with a water tank located above the device, the inlet and outlet ends of the channel are in communication with the atmosphere.