RU2313143C1 - Nuclear power plant - Google Patents

Abstract

FIELD: nuclear power engineering; liquid-metal cooled reactor units.

SUBSTANCE: proposed nuclear power plant has liquid-metal coolant, liquid lead or its alloys being used for the purpose, and shielding gas system. Reactor core, steam generators, and circulation facilities, such as circulating pumps, are disposed below coolant level. Annular channel whose inner diameter is greater than outer diameter of core is located above the latter. Steam generator segments whose inlet section communicates with coolant space under core and outlet one, with inlet chamber of pump located in same chamber are disposed in annular channel or in its sections. Pump pressure chamber communicates with reactor core.

EFFECT: reduced length of reactor circulating paths and coolant volume therein.

1 cl, 3 dwg

Description

The solution relates to nuclear engineering and can be used in reactor plants with liquid metal cooling.

A nuclear power plant is known that contains a reactor with a liquid metal lead coolant or its alloys, with an active zone, steam generators, circulation means, and a protective gas system placed under a free coolant level (Patent for the invention No. 2192052 of 10.27.2002, G21C 9/016, 19/19/19 / 28, 19/31).

The disadvantage of this technical solution in relation to nuclear power plants with lead coolant or its alloys is a loop arrangement, in which each pump provides circulation through only one steam generator of its loop. In the absence of shutoff valves that turn off the equipment of the heat transfer loop (steam generator-pump), this technical solution affects the survivability of the installation in emergency situations. In the known technical solution, the volume of coolant in the circuit is quite large due to the long and volume circulation channels, which affects the overall dimensions and economic performance of the installation. The latter is explained by the fact that the lead lead coolant is much more expensive than steel, and the lead-bismuth eutectic is much more expensive than lead.

The tasks solved by the invention are improving the design of a nuclear power plant, increasing its safety and efficiency.

The technical result is a decrease in the length of the circulation paths of the reactor circuit and the volume of coolant in it, a decrease in the overall dimensions of the reactor circuit.

The technical result is achieved by the fact that a nuclear power plant containing a reactor with liquid metal lead coolant or its alloys, with an active zone, steam generators, circulating means and a protective gas system placed under a free coolant level, is equipped with an annular channel placed above the active zone, the inner diameter of which larger than the outer diameter of the core, sections of steam generators are installed in the annular channel or in its sections, the inlet section of which is connected with the volume ohm of the coolant above the core, and the outlet section is with the pump inlet chamber located in the same channel, and the pressure chamber of the pump is communicated through the lowering channel with the reactor core.

Justification of the technical result: will reduce the hydraulic resistance of the reactor loop; increase the percentage of natural circulation in the circuit; to increase the safety of the reactor installation in case of emergency destruction of the tubes of the steam generator.

Figure 1 presents a diagram of a reactor installation in the context of a steam generator and a pump; figure 2 is a top view; figure 3 - part of the scan section of the annular channel.

In a nuclear reactor 1 containing liquid metal lead coolant or its alloys, an active zone 3, steam generators 4, circulation means, for example an axial pump 5, are located under the free level 2 of the coolant. Steam generators 4 and pump 5 are installed below the level of coolant 2 in the annular channel 6 located above the core 3. The inner diameter of the annular channel 6 is larger than the outer diameter of the core 3. The inlet section of the steam generators 4 is in communication with the volume 7 of the coolant above the core 3.

The output section of the steam generator 4 is in communication with the inlet pressure chamber 8 of the pump 5, located in the annular channel 6. The pressure chamber 8 of the pump 5 is communicated through the lower channel 10 with the active zone 3 of the reactor 1.

The operation of a nuclear power plant is as follows. The coolant is heated in the core 3 of the reactor 1 due to the heat released during the fission of heavy nuclei. The heated coolant enters volume 7 above the core 3 due to the operation of pump 5. From volume 7, the coolant enters the inlet sections of sections of the steam generators 4, washes the tubes of the steam generator located under free level 2 of the coolant, and gives off heat to the working medium circuit. From the output sections of the steam generators 4, the coolant enters the pressure chamber 8 of the pump 5. The pump 5 reports the flow of heat to the energy consumed to overcome the hydraulic resistance of the lower section 10 and core 3, as well as to raise the free level 2 of the coolant in the inlet sections of the steam generators 4, equal to the hydraulic resistance from the inlet sections of the steam generators 4 to the pump 5 suction. The flow of cooled coolant from the pressure chamber of the pump 5 through the lowering section 10 enters the active zone 3.

When the neutron power of the reactor changes from nominal to zero, the coolant flow rate changes, however, the above circulation sequence is preserved. When the pumps are stopped, with equal hydraulic resistances, a high-altitude arrangement of equipment and temperature differences, the flow rate of the coolant due to natural circulation in the proposed solution is the largest in comparison with other nuclear power plants.

The application of the proposed technical solution allows you to:

- reduce the length of the circulation paths of the reactor circuit and the volume of coolant in it;

- to reduce the weight and size characteristics of a nuclear power plant with liquid metal lead coolant or its alloys;

- increase the driving pressure of the natural circulation and the coolant flow rate of the reactor circuit in the natural circulation mode;

- simplify the design of a nuclear power plant and increase its efficiency.

Claims (1)

A nuclear power plant containing a reactor with a liquid metal lead coolant or its alloys, with an active zone, steam generators, circulation means, for example circulating pumps, placed under a free level of the coolant, and a protective gas system, characterized in that an annular channel is placed above the active zone, inner diameter which is larger than the outer diameter of the core, sections of steam generators are installed in the annular channel or in its sections, the inlet section of which is connected with the volume coolant above the core, and an outlet section - with the inlet chamber of the pump, for example axial, disposed in the same channel and the pressurized pump chamber communicates with the passage through the standpipe of the reactor core.

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