RU2424587C1 - Liquid salt nuclear reactor (versions) - Google Patents

Abstract

FIELD: power industry. ^ SUBSTANCE: liquid salt nuclear reactor is equipped with heat removal equipment, electric power generation equipment, reactor power control system and gas removal and cleaning system; housing of the above reactor is equipped at least with one inlet and outlet connection pipe of cooling heat carrier, and includes active zone chamber and moderator rods located in it. Above active zone chamber there installed is lower and upper tube grids with coincident holes for cooling heat carrier pipelines sealed in holes of tube grids and lowered to active zone chamber with "tube in tube" vapours; internal pipeline is installed with clearance for passage of cooling heat carrier in external pipeline plugged at the bottom; reactor is equipped with pipeline lowered to the bottom of active zone chamber and connected to branch pipe on reactor housing, which is intended to be connected to the equipment for filling of liquid salt chamber with liquid salt composition and emptying, pipeline connecting the dispergator located at that bottom of active zone chamber to branch pipe on reactor housing, which is intended to be connected to equipment of helium supply from gas removal and cleaning system, and at least one nuclear-safety expansion joint of thermal expansions of liquid salt fuel composition, which is connected to the top of active zone chamber and equipped with branch pipe to be connected to gas removal and cleaning system and level metre. ^ EFFECT: group of inventions allows designing safety liquid salt reactor. ^ 34 cl, 9 dwg

Description

The invention relates to nuclear energy and can be used to create a liquid salt nuclear reactor.

Known fast sodium-cooled reactor BN-600 (Usynin GB, Kusmartsev EV "Fast neutron reactors". Publishing house "Energoatomizdat", Moscow, 1985). The active zone of the BN-600 reactor is composed of hexagonal cassettes consisting of rod fuel elements (fuel elements).

The main disadvantages of the known device include:

- the complexity of the design of the rod fuel rods;

- the inability to remove from the fuel rods gaseous fission products. For this reason, by the end of the campaign, in each fuel rod, the excess pressure of gaseous fission products is calculated to increase to 4 MPa;

- excessive unnecessary complexity of the design of the reactor BN-600. Near the reactor core, three circulating pumps and six “sodium-sodium” heat exchangers that are not repairable are immersed in molten activated sodium. This equipment has nothing to do with the core operation;

- low reliability of the thermal circuit. At nuclear power plants with a BN-600 reactor, there is a constant threat of dangerous contact of molten sodium of the second circuit with water.

The closest in technical essence to the claimed liquid salt nuclear reactor (options) is a liquid salt thermal neutron multiplier reactor (MSBR-1000) (Blinkin V.L., Novikov V.M. "Liquid salt nuclear reactors", M .: Atomizdat, 1978 )

The known device is a reactor with a three-circuit heat removal system. The fuel liquid salt composition circulates through the reactor vessel in the primary circuit. The generated heat is transferred from the liquid salt fuel composition in the heat exchanger to the secondary salt liquid cooling coolant. The liquid salt coolant transfers heat to the steam generator. The thermal energy of the resulting superheated steam is converted into electric energy in a steam turbine generator.

The reactor is equipped with equipment for a reactor power control system, a gas removal and purification system.

The main disadvantages of MSBR include the following:

- a large amount of fuel is located outside the reactor vessel, in pipelines and other equipment of the circulation circuit of the liquid salt fuel composition;

- the complexity of the design of the heat removal system from the reactor;

- liquid salt fuel composition is supplied to the reactor vessel from below. If a defect occurs in the weld connecting the inlet to the reactor vessel, the liquid-salt fuel composition may leak out of the reactor vessel;

- when the fuel is circulated through the reactor, a part of the delayed neutrons leaves the active zone with the fuel flow, therefore, the reactivity of the reactor with circulating fuel is less than the reactivity of the reactor with fuel not leaving the casing.

The technical result of the invention consists in the development of a safe liquid salt reactor equipped with thermal neutron exhaust and gas purification system equipment, with a reliable housing, a simple and reliable heat removal system that can be operated as part of a transport power plant.

To achieve a technical result in a liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system and a gas removal and purification system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains a core of the active zone and the retarder rods located in it, it is proposed:

- install the lower and upper tube sheets above the active zone chamber with matching holes for cooling coolant pipelines, sealed in the holes of the tube sheets and lowered into the core chamber by “pipe in pipe” pairs, the inner pipe is installed with a clearance for the passage of coolant in an external, muffled down the pipeline;

- the reactor is equipped with a pipe, lowered to the bottom of the core of the core, connected to a pipe on the reactor vessel, designed to be connected to the filling equipment of the core of the core with a liquid salt fuel composition and emptying;

- to provide the reactor with a pipeline connecting the dispersant located at the bottom of the active chamber with a nozzle on the reactor vessel designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition, connected with the top of the core of the core and equipped with a pipe for connecting to a gas removal and purification system and a level gauge.

In special cases, the execution of a liquid salt nuclear reactor is proposed:

- on the pairs of pipelines of the cooling coolant to establish coaxially and with a clearance the retarder rods having above and below the holes for the natural circulation of the cooled liquid salt fuel-containing composition;

- in the chamber of the active zone, select the outer annular region in which pairs of pipelines of the cooling coolant to install with a large step;

- equip the reactor with a partition that forms the central chamber of the active zone and the peripheral chamber of the nuclear fuel reproduction zone, provide a pipe connected to the nozzle on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, for connecting to the filling equipment of the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant located at the bottom of the chamber of the reproduction zone with the nozzle on the reactor vessel, designed to connect Nia equipment supply of helium gas collection and treatment system, and at least one compensator safe nuclear thermal expansions Molten salt feedstock composition, coupled with horse blanket and fitted with a nozzle chamber for connecting to the gas discharge system and purification by level;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium - gaseous medium, and a circulation pump for the liquid-medium cooling medium, and equipment for the circulation circuit of the gaseous medium, which includes the liquid-medium cooling medium - ”, Gas turbine generator and compressor;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes the heat-exchanger "liquid salt cooling medium - steam-water medium" and a circulation pump for the liquid-salt medium, and equipment for the circulation circuit of the steam-water medium, which includes the heat-exchange medium, heat-medium ”, Steam turbine generator and feed pump;

- to equip the reactor with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor;

- to equip the reactor with equipment for cooling the reactor with a steam-water cooling medium, which includes a steam turbine generator and a feed pump.

The invention is illustrated by drawings, where figure 1-9 shows a possible design of a liquid salt nuclear reactor with thermal neutrons, without a separated partition of the reproduction zone, and also a possible design of a liquid salt nuclear reactor with thermal neutrons with a separated partition of the reproduction zone. The operation of these reactors is greatly simplified due to the lack of fuel processing system equipment in them, so they can be operated as part of a transport power plant.

In figure 1, 3, 6-9 adopted the following notation:

1 - lateral neutron reflector, 2 - upper end neutron reflector, 3 - upper tube sheet, 4 - external coolant pipe, 5 - internal coolant pipe, 6 - inlet pipe for coolant, 7 - outlet pipe for coolant, 8 - gas turbine generator 9 - dispersant located at the bottom of the core of the core, 11 (1) - freezing valve, 12 (1) - shut-off valve, 13 - core of the core, 15 - compressor, 16 - reactor vessel, 17 - lower end neutron reflector, 18 - lower tr gas grid, 19 - steam turbine generator, 20 - disperser pipe located at the bottom of the core, 22 - filling pipe - emptying the core, 24 - expansion joint pipe for thermal expansion of the liquid salt fuel composition, 27 - feed pump, 29 - gas removal and purification system , 30 - retarder rod, 31 - reactor power control rod, 32 - liquid-salt cooling coolant-gaseous heat exchanger heat exchanger, 33 - liquid-salt cooling coolant-steam-water heat exchanger heat exchanger Itel ”, 34 — pipeline of the dispersant located at the bottom of the core of the core, 37 — pipe of filling — emptying of the core, 39 (1) - level gauge, 40 — circulation pump for the liquid salt coolant, 41 — nuclear-safe compensator for thermal expansions of the liquid salt fuel composition .

The composition of a liquid-salt thermal neutron nuclear reactor, without a reproduction zone separated by a partition, includes:

Equipment for heat removal, power generation, reactor power control system and gas removal and purification system 29. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 pipes of the cooling fluid and containing a core 13 and the moderator rods 30 located therein. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipes, sealed in the holes of the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of the cooling medium in external 4, plugged at the bottom of the pipeline. Pipeline 37, lowered to the bottom of the core chamber 13, connected to a pipe 22 on the reactor housing 16, intended for connection to the core filling chamber equipment with a liquid salt fuel composition and emptying. A pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29. At least one nuclear-safe compensator 41 for thermal expansions of the liquid salt fuel composition connected to the top of the core 13 and provided with a pipe 24 for connection to the gas removal and purification system 29 and the level gauge 39 (1).

In addition, the composition of the liquid-salt nuclear reactor includes not shown in the drawings all electric heaters and thermal insulation of the housing 16 and other equipment.

In special cases, the execution of a liquid-salt nuclear reactor may include:

Installed coaxially and with a clearance on the pairs of pipelines of the cooling coolant, retarder rods 30 having holes at the top and bottom for the natural circulation of the cooled liquid salt fuel-containing composition. The chamber 13 of the active zone with a distinguished external annular region in which pairs of pipelines of the cooling coolant are installed with a large pitch. Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", Gas turbine generator 8 and compressor 15. Equipment for cooling the reactor with liquid-salt cooling t a carrier, which includes a heat exchanger 33 "liquid-salt cooling medium - a steam-water coolant" and a circulation pump 40 of a liquid-salt cooling medium, and equipment for the circulation circuit of a steam-water medium, which includes a heat exchanger 33 "a liquid-salt cooling medium - a steam-water medium, 19 steam turbine pump 27. Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 15. A compressor for cooling the steam-cooling equipment of reactor coolant, which comprises steam turbine generator 19 and the feed pump 27.

In addition, the composition of the liquid salt reactor may include: Lower 17 and upper 2 end and side 1 neutron reflectors. The rods 31 control the power of the reactor. Freezing valve 11 (1). Stop valve 12 (1).

The equipment for heat removal and power generation is designed to use the heat generated in the reactor. The equipment of the reactor power control system is designed to control its reactivity. The equipment of the gas removal and purification system 29 is designed to collect gaseous fission products by sparging helium with a liquid salt fuel composition, purifying them from impurities and disposing. Any other inert gas may be used for sparging. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 coolant coolant pipes, is designed to accommodate the core chamber 13 with internal 5 and external 4 coolant pipes and retarder rods 30 located therein. The direction of the entrance of the cooling fluid into the reactor vessel 16 and the exit from the reactor vessel 16 can be changed by interchanging the inlet 6 and outlet 7 pipes. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching openings for the coolant pipes, sealed along the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of coolant into external 4, plugged at the bottom of the pipeline, are designed for the necessary distribution of the cooling fluid along the cross section of the active zone. The pipe 22 on the reactor housing 16 and the pipe 37 connected to it, lowered to the bottom of the chamber 13 of the active zone, are intended to be connected to the filling equipment of the chamber 13 of the active zone with a liquid-salt fuel composition and emptying. A pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16 for connecting to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe liquid-salt thermal expansion joint 41 the fuel composition, connected to the top of the chamber 13 of the active zone and equipped with a pipe 24 for connection with the system 29 removal and purification of gases and the level gauge 39 (1), are designed to remove gaseous fission products from the core ernogo fuel. In addition, at least one nuclear-safe compensator 41 for thermal expansions of the liquid-salt fuel composition connected to the top of the core 13 is designed to eliminate the possibility of gas cavities at the top of the core 13 and thereby keep the core geometry unchanged when the reactor is tilted .

Not shown in the drawings, electric heaters and thermal insulation are designed to heat the housing 16 and other equipment to temperatures exceeding the melting temperature of the liquid salt compositions, and reduce heat loss.

The moderator rods 30, mounted coaxially and with a gap on the pairs of cooling coolant pipelines and having holes at the top and bottom, are designed to slow down neutrons to thermal energy and ensure natural circulation of the cooled liquid-salt fuel-containing composition in the reactor.

The outer annular region in the chamber 13 of the active zone, in which pairs of coolant coolant pipelines are installed in large increments, is intended to form a secondary fuel reproduction zone by reducing the volume fraction of the moderator in it and increasing the volume fraction of the liquid salt fuel composition. In the thus selected region of the active zone, the reproduction of secondary nuclear fuel will proceed more intensively.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", A gas turbine generator 8 and compressor 15, are designed to remove heat from the reactor and to produce electric energy.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 33 "liquid-salt cooling medium - steam-water medium" and a salt-water circulation pump 40, and equipment for a steam-water medium circulation circuit, which includes a heat-exchanger 33 "liquid-salt cooling medium - a steam-water medium A steam turbine generator 19 and a feed pump 27 are also provided for removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 and compressor 15, is designed to implement the third option of removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a steam-water cooling coolant, which includes a steam turbine generator 19 and a feed pump 27, is designed to implement the fourth variant of heat removal from the reactor and the production of electricity.

The lower 17 and upper 2 end and side 1 neutron reflectors are designed to reduce neutron leakage from the core. The power control rods 31 are for controlling the reactivity of the reactor.

The freezing valve 11 (1) is designed to seal the chamber 13 of the active zone. The shut-off valve 12 (1) is intended for connection with the equipment of a gas station or a refueling vessel during reactor overloads through, for example, a removable filling-emptying pipeline.

The nozzles connecting the reactor vessel 16 to the operating systems must be installed on the vessel 16 above the level of the liquid salt fuel composition in at least one expansion joint 41 of the thermal expansion of the fuel composition so that in case of a defect in any of the nozzles the fuel could not leak from the chamber 13 of the active zone.

A liquid salt nuclear reactor as part of a transport installation operates as follows.

The shut-off valve 12 (1) is connected with a removable filling-emptying pipe to the nuclear-safe tank of the gas station filled with the fuel composition. They supply power to the equipment of the transport installation from a backup power source or from a gas station. They apply voltage to the electric heaters of the housing 16, pipe 22, freezing valve 11 (1), shut-off valve 12 (1), a removable filling-emptying pipeline, a circulation pump 40 for a liquid-salt cooling medium, a heat exchanger 32 "liquid-salt cooling medium - a gaseous heat transfer medium", pipelines and other equipment that circulates the liquid salt coolant. The equipment is warmed up to the required temperature exceeding the temperature of the liquid-salt medium in it. Fill the circulation loop of the liquid salt coolant. Turn on the circulation pump 40 and pump the liquid salt cooling coolant through the reactor. From the nuclear-safe tank of the filling station, through the shut-off valve 12 (1), the freezing valve 11 (1) and the nozzle 22 fill the chamber 13 of the active zone with a liquid-salt fuel composition according to the readings of the level gauge 39 (1) in the nuclear-safe compensator 41 for thermal expansion of the liquid-salt fuel composition . The shut-off valve 12 (1) is closed and cooling is supplied to the freezing valve 11 (1). Remove the removable filling-emptying pipeline. By means of control rods 31, the reactor is brought to the required power level. The lower 17 and upper 2 end and side 1 neutron reflectors will reduce neutron leakage outside the core 13, and the moderator rods 30 will provide the neutron thermal spectrum in it. The reactor will run on thermal neutrons. In the chamber 13 of the active zone, in the space between the moderator rods 30 and in the gaps between the moderator rods 30 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt fuel composition will be established.

Turn on the compressor 15 and pump the gaseous coolant in the circuit. The liquid-salt cooling fluid heated in the core 13 will transfer heat in the heat exchanger 32 to the gaseous fluid. The gaseous coolant will spend the received energy in the gas turbine generator 8 to generate electricity.

When the heat exchanger 32 "liquid salt cooling medium - gaseous liquid medium" is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

To remove gaseous fission products from the chamber 13 of the active zone, helium is supplied through the nozzle 20 and dispersant 9 from the gas removal and purification system 29. Gaseous fission products released together with helium into the compensation chamber of the nuclear-safe compensator 41 for thermal expansions of the liquid-salt fuel composition are pumped out to the equipment of system 29, where they are cleaned of impurities and disposed of.

In order to replace the fuel composition, stop the reactor, connect the shut-off valve 12 (1) with a removable pipe to the nuclear-safe tank of the gas station, stop cooling the freezing valve 11 (1), warm it to a temperature higher than the melting temperature of the fuel composition, open the shut-off valve 12 ( 1) and the spent fuel composition is poured from the core chamber 13 into a nuclear-safe tank of a gas station. Close the shut-off valve 12 (1), connect the removable pipe to the nuclear-safe tank with a fresh fuel composition. The shut-off valve 12 (1) is opened and the core chamber 13 is filled with a fresh fuel composition from the nuclear-safe tank of the gas station. Close the shut-off valve 12 (1) and freeze the valve 11 (1). They launch the reactor into operation and bring it to the required power level.

Another option is the heat removal from the reactor. The feed pump 27 is turned on and the steam-water coolant is pumped in its circulation circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling medium transfers heat in the heat exchanger 33 to the steam-water medium. Steam-water coolant spends the received energy in the steam turbine 19 to generate electricity.

When the heat exchanger 33 “liquid salt cooling medium - steam-water medium” is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

A third option is the heat removal from the reactor. The compressor 15 is turned on and the gaseous cooling medium is pumped through the reactor. The reactor is brought to the required power level. The gaseous cooling medium heated in the core and in the reproduction zone will spend the energy received in the gas turbine generator 8 to generate electricity.

A fourth variant of heat removal from the reactor is possible. The feed pump 27 is turned on and the steam-water coolant is pumped through the reactor. The reactor is brought to the required power level. The superheated steam obtained in the active zone and the reproduction zone will spend the received energy in the steam turbine generator 19 for the production of electricity.

When the steam turbine generator 19 is located above the reactor, the process of natural circulation of the steam-water coolant is established in the circulation circuit of the steam-water coolant. The natural circulation of the steam-water coolant will significantly reduce the load on the feed pump 27 and increase the safety of the reactor.

The developed reactor is a reactor with liquid fuel elements in which stress states do not arise with temperature changes. Therefore, it can operate in the mode of variable loads, and at the same time, no stresses associated with thermocyclic loads occur in its design. The temperature coefficient of reactivity of this reactor is always negative. The reactor has increased controllability and reliability, since the fuel liquid-salt composition does not go beyond the reactor vessel when heat is removed from it and all delayed neutrons remain in the active zone.

During wave oscillations or take-off and landing, inclinations of a reactor operating as part of a transport installation are possible. When tilting the reactor, at least one nuclear-safe compensator 41 will ensure the invariance of the geometry of the active zone.

An example of a specific embodiment of a liquid salt nuclear reactor.

For an example of a specific implementation, a liquid-salt nuclear reactor is taken - a thermal neutron converter with a uranium-thorium fuel cycle, i.e. fissile material is, for example, uranium-235, the raw material of thorium-232, and reproducible fuel is uranium-233. The reproduction coefficient of the reactor will be less than unity, but close to it. As the fuel composition, a mixture of fluoride salts, for example 71.772 ⁷ LiF-16.0 BeF ₂ -12.0ThF ₄ -0.228UF _4, can be selected. As a liquid-salt coolant, a eutectic mixture 92, ONaBF4-8, ONaF, which has a lower melting point, can be selected. As the main structural material can be selected alloy hastelloy - N. The molar composition of the alloy hastelloy - N,%: Ni 66,0; Mo 17.0; Cr 7.0; Fe 5.0.

The technical result of the invention is obtained, a safe liquid-salt thermal-neutron reactor is developed with a reliable body and a simple and reliable heat removal system that can be operated as part of a transport power plant.

A liquid salt thermal neutron reactor for a transport power plant having a reproduction zone separated by a partition is shown in FIGS. 1, 3, 5-9. Refueling and replacing the fuel and raw material compositions of this reactor from the gas station will need to be done through two removable filling and discharge pipelines.

A similar design may have a reactor for transport installations using thermal neutrons with liquid metal fuel.

Known fast sodium-cooled reactor BN-600 (Usynin GB, Kusmartsev EV "Fast neutron reactors." Publishing house "Energoatomizdat", Moscow, 1985). The active zone of the BN-600 reactor is composed of hexagonal cassettes consisting of rod fuel elements (fuel elements).

The main disadvantages of the known device include:

- the complexity of the design of the rod fuel rods;

- the inability to remove from the fuel rods gaseous fission products. For this reason, by the end of the campaign, in each fuel rod, the excess pressure of gaseous fission products is calculated to increase to 4 MPa;

- excessive unnecessary complexity of the design of the reactor BN-600. Near the reactor core, three circulating pumps and six “sodium-sodium” heat exchangers that are not repairable are immersed in molten activated sodium. This equipment has nothing to do with the core operation;

- low reliability of the thermal circuit. At nuclear power plants with a BN-600 reactor, there is a constant threat of dangerous contact of molten sodium of the second circuit with water.

The closest in technical essence to the claimed liquid salt nuclear reactor (options) is a liquid salt thermal neutron multiplier reactor (MSBR-1000) (Blinkin V.L., Novikov V.M. "Liquid salt nuclear reactors", M .: Atomizdat, 1978 )

The known device is a reactor with a three-circuit heat removal system. The fuel liquid salt composition circulates through the reactor vessel in the primary circuit. The generated heat is transferred from the liquid salt fuel composition in the heat exchanger to the secondary salt liquid cooling coolant. The liquid salt coolant transfers heat to the steam generator. The thermal energy of the resulting superheated steam is converted into electric energy in a steam turbine generator.

The reactor is equipped with equipment for a reactor power control system, a gas removal and purification system.

The main disadvantages of MSBR include:

- a large amount of fuel is located outside the reactor vessel, in pipelines and other equipment of the circulation circuit of the liquid salt fuel composition;

- the complexity of the design of the heat removal system from the reactor;

- liquid salt fuel composition is supplied to the reactor vessel from below. If a defect occurs in the weld connecting the inlet to the reactor vessel, the liquid-salt fuel composition may leak out of the reactor vessel;

- when the fuel is circulated through the reactor, a part of the delayed neutrons leaves the active zone with the fuel flow, therefore, the reactivity of the reactor with circulating fuel is less than the reactivity of the reactor with fuel not leaving the casing.

The technical result of the invention consists in the development of a safe fast-neutron liquid salt reactor with a reliable housing, a simple and reliable heat removal system that can be operated as part of a transport power plant.

To achieve a technical result in a liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system and a gas removal and purification system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains a core of the active zone , offered:

- install the lower and upper tube sheets above the chamber of the core with matching holes for the coolant pipelines, sealed in the holes of the tube sheets and lowered into the chamber of the core in pairs "pipe in pipe", install the inner pipe with a clearance for the passage of coolant in an external, muffled down the pipeline;

- the reactor is equipped with a pipe, lowered to the bottom of the core of the core, connected to a pipe on the reactor vessel, designed to be connected to the filling equipment of the core of the core with a liquid salt fuel composition and emptying;

- to provide the reactor with a pipeline connecting the dispersant located at the bottom of the active chamber with a nozzle on the reactor vessel designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition, connected with the top of the core of the core and equipped with a pipe for connecting to a gas removal and purification system and a level gauge.

In special cases, the execution of a liquid salt nuclear reactor is proposed:

- on the pairs of pipelines of the cooling coolant to establish coaxially and with a clearance pipelines having above and below the holes for the natural circulation of the cooled liquid salt fuel-containing composition;

- in the chamber of the active zone, select the outer annular region in which pairs of pipelines of the cooling coolant to install with a large step;

- equip the reactor with a partition that forms the central chamber of the active zone and the peripheral chamber of the nuclear fuel reproduction zone, provide a pipe connected to the nozzle on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, for connecting to the filling equipment of the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant located at the bottom of the chamber of the reproduction zone with the nozzle on the reactor vessel, designed to connect Nia equipment supply of helium gas collection and treatment system, and at least one compensator safe nuclear thermal expansions Molten salt feedstock composition, coupled with horse blanket and fitted with a nozzle chamber for connecting to the gas discharge system and purification by level;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium - gaseous medium, and a circulation pump for the liquid-medium cooling medium, and equipment for the circulation circuit of the gaseous medium, which includes the liquid-medium cooling medium - ”, Gas turbine generator and compressor;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes the heat-exchanger "liquid salt cooling medium - steam-water medium" and a circulation pump for the liquid-salt medium, and equipment for the circulation circuit of the steam-water medium, which includes the heat-exchange medium, heat-medium ”, Steam turbine generator and feed pump;

- to equip the reactor with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor.

The invention is illustrated by drawings, where figure 2, 4, 6-9 shows a possible design of a liquid-salt fast-neutron nuclear reactor without a separated reproduction zone, and figure 2, 4, 5-9 shows a possible design of a liquid-salt nuclear reactor fast neutrons, with a septum-separated reproduction zone. The operation of these reactors is greatly simplified due to the lack of fuel processing system equipment in them, so they can be operated as part of a transport power plant.

In figure 2, 4, 6-9 the following notation:

1 - lateral neutron reflector, 2 - upper end neutron reflector, 3 - upper tube sheet, 4 - external coolant pipe, 5 - internal coolant pipe, 6 - inlet pipe for coolant, 7 - outlet pipe for coolant, 8 - gas turbine generator 9 - dispersant located at the bottom of the core of the core, 11 (1) - freezing valve, 12 (1) - shut-off valve, 13 - core of the core, 15 - compressor, 16 - reactor vessel, 17 - lower end neutron reflector, 18 - lower tr gas grid, 19 - steam turbine generator, 20 - disperser pipe located at the bottom of the core, 22 - filling pipe - emptying the core, 24 - expansion joint pipe for thermal expansion of the liquid salt fuel composition, 27 - feed pump, 29 - gas removal and purification system 31 - reactor power control rod, 32 - liquid-salt cooling coolant-gaseous coolant heat exchanger, 33 - liquid-salt cooling coolant-steam-water coolant heat exchanger, 34 - pipeline d a sparger located at the bottom of the core, 36 — a pipeline for the natural circulation of a cooled liquid-salt fuel-containing composition, 37 — a filling pipeline — emptying the core of a core, 39 (1) —a level gauge, 40 — a circulation pump for a liquid-salt cooling medium, 41 — a nuclear-safe compensator thermal expansions of the liquid salt fuel composition.

The composition of a liquid-salt fast-neutron nuclear reactor, without a reproduction zone separated by a partition, includes:

Equipment for heat removal, power generation, reactor power control system and gas removal and purification system 29. The housing 16 of the reactor, equipped with at least one inlet 6 and one outlet 7 pipes of the cooling fluid and containing a chamber 13 of the active zone. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipes, sealed in the holes of the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of the cooling medium in external 4, plugged at the bottom of the pipeline. Pipeline 37, lowered to the bottom of the core chamber 13, connected to a pipe 22 on the reactor housing 16, intended for connection to the core filling chamber equipment with a liquid salt fuel composition and emptying. A pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29. At least one nuclear-safe compensator 41 for thermal expansions of the liquid salt fuel composition connected to the top of the core 13 and provided with a pipe 24 for connection to the gas removal and purification system 29 and the level gauge 39 (1).

In addition, the composition of the liquid-salt nuclear reactor includes not shown in the drawings all electric heaters and thermal insulation of the housing 16 and other equipment.

In special cases, the execution of a liquid-salt nuclear reactor may include:

Installed coaxially and with a clearance on the pairs of pipelines of the cooling fluid, pipelines 36 having openings at the top and bottom for the natural circulation of the cooled liquid-salt fuel-containing composition. The chamber 13 of the active zone with a distinguished external annular region in which pairs of pipelines of the cooling coolant are installed with a large pitch. Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", Gas turbine generator 8 and compressor 15. Equipment for cooling the reactor with liquid-salt cooling t a carrier, which includes a heat exchanger 33 "liquid-salt cooling medium - a steam-water coolant" and a circulation pump 40 of a liquid-salt cooling medium, and equipment for the circulation circuit of a steam-water medium, which includes a heat exchanger 33 "a liquid-salt cooling medium - a steam-water medium, 19 steam turbine pump 27. Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 compressor 15.

In addition, the composition of the liquid salt reactor may include: Lower 17 and upper 2 end and side 1 neutron reflectors. The rods 31 control the power of the reactor. Freezing valve 11 (1). Stop valve 12 (1).

The equipment for heat removal and power generation is designed to use the heat generated in the reactor. The equipment of the reactor power control system is designed to control its reactivity. The equipment of the gas removal and purification system 29 is designed to collect gaseous fission products by sparging helium with a liquid salt fuel composition, purifying them from impurities and disposing. Any other inert gas may be used for sparging. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 nozzles of the cooling coolant, is designed to accommodate the chamber 13 of the active zone with the internal 5 and external 4 pipelines of the cooling coolant. The direction of the entrance of the cooling fluid into the reactor vessel 16 and the exit from the reactor vessel 16 can be changed by interchanging the inlet 6 and outlet 7 pipes. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching openings for the coolant pipes, sealed along the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of coolant into external 4 plugged at the bottom of the pipeline, designed for the necessary distribution of the cooling fluid along the cross section of the active zone. The pipe 22 on the reactor housing 16 and the pipe 37 connected to it, lowered to the bottom of the chamber 13 of the active zone, are intended to be connected to the filling equipment of the chamber 13 of the active zone with a liquid-salt fuel composition and emptying. Pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16 for connecting to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe expansion joint 41 liquid-salt fuel composition, connected to the top of the chamber 13 of the active zone and equipped with a pipe 24 for connection with the system 29 removal and purification of gases and the level gauge 39 (1), are designed to remove gaseous fission products from the active zone nuclear fuel. In addition, at least one nuclear-safe compensator 41 for thermal expansions of the liquid-salt fuel composition connected to the top of the core 13 is designed to eliminate the possibility of gas cavities at the top of the core 13 and thereby keep the core geometry unchanged when the reactor is tilted .

Electric heaters and thermal insulation not shown in the figures are designed to heat the housing 16 and other equipment to temperatures exceeding the melting temperature of liquid-salt compositions and reduce heat loss.

Pipelines 36, installed coaxially and with a gap on the pairs of pipelines of the cooling fluid and having holes at the top and bottom, are designed to provide natural circulation of the cooled liquid-salt fuel-containing composition in the reactor.

The outer annular region in the chamber 13 of the active zone, in which pairs of coolant coolant pipelines are installed in large increments, is intended to form a secondary fuel reproduction zone by increasing the volume fraction of the liquid salt fuel composition in it. In the thus selected region of the active zone, the reproduction of nuclear fuel will proceed more intensively.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", A gas turbine generator 8 and compressor 15, are designed to remove heat from the reactor and to produce electric energy.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 33 "liquid-salt cooling medium - steam-water medium" and a salt-water circulation pump 40, and equipment for a steam-water medium circulation circuit, which includes a heat-exchanger 33 "liquid-salt cooling medium - a steam-water medium A steam turbine generator 19 and a feed pump 27 are also provided for removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 and compressor 15, is designed to implement the third option of removing heat from the reactor and generating electricity.

The lower 17 and upper 2 end and side 1 neutron reflectors are designed to reduce neutron leakage from the core. The power control rods 31 are for controlling the reactivity of the reactor.

The freezing valve 11 (1) is designed to seal the chamber 13 of the active zone. The shut-off valve 12 (1) is intended for connection with the equipment of a gas station or a refueling vessel during reactor overloads through, for example, a removable filling-emptying pipeline.

The nozzles connecting the reactor vessel 16 to the operating systems must be installed on the vessel 16 above the level of the liquid salt fuel composition in at least one expansion joint 41 of the thermal expansion of the fuel composition so that in case of a defect in any of the nozzles the fuel could not leak from the chamber 13 of the active zone.

A liquid salt nuclear reactor as part of a transport installation operates as follows.

The shut-off valve 12 (1) is connected with a removable filling-emptying pipe to the nuclear-safe tank of the gas station filled with the fuel composition. They supply power to the equipment of the transport installation from a backup power source or from a gas station. They apply voltage to the electric heaters of the housing 16, pipe 22, freezing valve 11 (1), shut-off valve 12 (1), a removable filling-emptying pipe, a circulation pump 40 for a liquid-salt cooling medium, a heat exchanger 32 "liquid-salt cooling medium for a gaseous heat transfer medium", pipelines and other equipment that circulates the liquid salt coolant. The equipment is warmed up to the required temperature exceeding the temperature of the liquid-salt medium in it. Fill the circulation loop of the liquid salt coolant. Turn on the circulation pump 40 and pump the liquid salt cooling coolant through the reactor. From the nuclear-safe tank of the filling station, through the shut-off valve 12 (1), the freezing valve 11 (1) and the nozzle 22 fill the chamber 13 of the active zone with a liquid salt fuel composition according to the readings of the level gauge 39 (1) in the nuclear-safe compensator 41 for thermal expansion of the liquid salt fuel composition . The shut-off valve 12 (1) is closed and cooling is supplied to the freezing valve 11 (1). Remove the removable filling-emptying pipeline. By means of control rods 31 will bring the reactor to the required power level. The lower 17 and upper 2 end and side 1 neutron reflectors will reduce neutron leakage outside the core 13. Due to the absence of a moderator in the core, a fast neutron spectrum will be established. The reactor will run on fast neutrons. In the chamber 13 of the active zone, in the space between the pipelines 36 and in the gaps between the pipelines 36 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt fuel composition will be established.

Turn on the compressor 15 and pump the gaseous coolant in the circuit. The liquid-salt cooling fluid heated in the core 13 will transfer heat in the heat exchanger 32 to the gaseous fluid. The gaseous coolant will spend the received energy in the gas turbine generator 8 to generate electricity.

When the heat exchanger 32 "liquid salt cooling medium - gaseous liquid medium" is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

To remove gaseous fission products from the chamber 13 of the active zone, helium is supplied through the nozzle 20 and dispersant 9 from the gas removal and purification system 29. Gaseous fission products released together with helium into the compensation chamber of the nuclear-safe compensator 41 for thermal expansions of the liquid-salt fuel composition are pumped out to the equipment of system 29, where they are cleaned of impurities and disposed of.

In order to replace the fuel composition, stop the reactor, connect the shut-off valve 12 (1) with a removable pipe to the nuclear-safe tank of the gas station, stop cooling the freezing valve 11 (1), warm it to a temperature higher than the melting temperature of the fuel composition, open the shut-off valve 12 ( 1) and the spent fuel composition is poured from the core chamber 13 into a nuclear-safe tank of a gas station. Close the shut-off valve 12 (1), connect the removable pipe to the nuclear-safe tank with a fresh fuel composition. Open the shut-off valve 12 (1) and fill the core chamber 13 with a fresh fuel composition from a nuclear-safe tank of a gas station. Close the shut-off valve 12 (1) and freeze the valve 11 (1). They launch the reactor into operation and bring it to the required power level.

Another option is the heat removal from the reactor. The feed pump 27 is turned on and the steam-water coolant is pumped in its circulation circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling medium transfers heat in the heat exchanger 33 to the steam-water medium. Steam-water coolant spends the received energy in the steam turbine 19 to generate electricity.

When the heat exchanger 33 “liquid salt cooling medium - steam-water medium” is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

A third option is the heat removal from the reactor. The compressor 15 is turned on and the gaseous cooling medium is pumped through the reactor. The reactor is brought to the required power level. The gaseous cooling medium heated in the core and in the reproduction zone will spend the energy received in the gas turbine generator 8 to generate electricity.

The developed reactor is a reactor with liquid fuel elements in which stress states do not arise with temperature changes. Therefore, it can operate in the mode of variable loads and at the same time, no stresses associated with thermocyclic loads occur in its design. The temperature coefficient of reactivity of this reactor is always negative. The reactor has increased controllability and reliability, since the fuel liquid-salt composition does not go beyond the reactor vessel when heat is removed from it and all delayed neutrons remain in the active zone.

During wave oscillations or take-off and landing, inclinations of a reactor operating as part of a transport installation are possible. When tilting the reactor, at least one nuclear-safe compensator 41 will ensure the invariance of the geometry of the active zone.

An example of a specific embodiment of a liquid salt nuclear reactor.

For an example of a specific implementation, a liquid-salt nuclear reactor is taken - a thermal neutron converter with a uranium-thorium fuel cycle, i.e. fissile material is, for example, uranium-235, the raw material of thorium-232, a. reproducible fuel uranium-233. The reproduction coefficient of the reactor will be less than unity, but close to it. As the fuel composition, a mixture of fluoride salts, for example 71.772 ⁷ LiF-16.0 BeF ₂ -12.0ThF ₄ -0.228UF _4, can be selected. As a liquid-salt coolant, a eutectic mixture of 92.0NaBF ₄ -8.0NaF, which has a lower melting point, can be selected. As the main structural material can be selected alloy hastelloy-N. The molar composition of the Hastelloy-N alloy,%: Ni 66.0; Mo 17.0; Cr 7.0; Fe 5.0.

The technical result of the invention was obtained, a safe fast-neutron liquid-salt reactor was developed with a reliable housing and a simple and reliable heat removal system that could be operated as part of a transport power plant.

A liquid salt fast neutron reactor for a transport power plant, having a reproduction zone separated by a partition, is shown in FIGS. 2, 4, 5-9. Refueling and replacing the fuel and raw material compositions of this reactor from the gas station can be done through two removable filling and discharge pipelines.

A similar design may have a fast neutron reactor for a transport installation with liquid metal fuel.

Known fast sodium-cooled reactor BN-600 (Usynin GB, Kusmartsev EV "Fast neutron reactors". Publishing house "Energoatomizdat", Moscow, 1985). The active zone of the BN-600 reactor is composed of hexagonal cassettes consisting of rod fuel elements (fuel elements).

The main disadvantages of the known device include:

- the complexity of the design of the rod fuel rods;

- the inability to remove from the fuel rods gaseous fission products. For this reason, by the end of the campaign, in each fuel rod, the excess pressure of gaseous fission products is calculated to increase to 4 MPa;

- excessive unnecessary complexity of the design of the reactor BN-600. Near the reactor core, three circulating pumps and six “sodium-sodium” heat exchangers that are not repairable are immersed in molten activated sodium. This equipment has nothing to do with the core operation;

- low reliability of the thermal circuit. At nuclear power plants with a BN-600 reactor, there is a constant threat of dangerous contact of molten sodium of the second circuit with water.

The closest in technical essence to the claimed liquid salt nuclear reactor (options) is a liquid salt thermal neutron multiplier reactor (MSBR-1000) (Blinkin V.L., Novikov V.M. "Liquid salt nuclear reactors", M .: Atomizdat, 1978 )

The known device is a reactor with a three-circuit heat removal system. The fuel oil-salt composition circulates through the reactor vessel in the primary circuit. The generated heat is transferred from the liquid salt fuel composition in the heat exchanger to the secondary salt liquid cooling coolant. The liquid salt coolant transfers heat to the steam generator. The thermal energy of the resulting superheated steam is converted into electric energy in a steam turbine generator.

The reactor is equipped with equipment for a reactor power control system, a gas removal and purification system.

The main disadvantages of MSBR include:

- a large amount of fuel is located outside the reactor vessel, in pipelines and other equipment of the circulation circuit of the liquid salt fuel composition;

- the complexity of the design of the heat removal system from the reactor;

- liquid salt fuel composition is supplied to the reactor vessel from below. If a defect occurs in the weld connecting the inlet to the reactor vessel, the liquid-salt fuel composition may leak out of the reactor vessel;

- when the fuel is circulated through the reactor, a part of the delayed neutrons leaves the active zone with the fuel flow, therefore, the reactivity of the reactor with circulating fuel is less than the reactivity of the reactor with fuel not leaving the casing.

The technical result of the invention is to develop a safe liquid salt thermal neutron reactor equipped with fuel processing equipment with a reliable body, a simple and reliable heat removal system that can be operated as part of a nuclear power plant and a transport power plant.

To achieve a technical result in a liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, a gas removal and purification system, and a fuel processing system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains a core chamber and moderator rods located in it, it is proposed:

- install the lower and upper tube sheets above the active zone chamber with matching holes for cooling coolant pipelines, sealed in the holes of the tube sheets and lowered into the core chamber by “pipe in pipe” pairs, the inner pipe is installed with a clearance for the passage of coolant in an external, muffled down the pipeline;

- the reactor is equipped with a pipe, lowered to the bottom of the core of the core, connected to a pipe on the reactor vessel, designed to be connected to the filling equipment of the core of the core with a liquid salt fuel composition and emptying;

- to provide the reactor with a pipeline connecting the dispersant located at the bottom of the active chamber with a nozzle on the reactor vessel designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition, connected with the top of the core of the core and equipped with a pipe for connecting to a gas removal and purification system and a level gauge.

In special cases, the execution of a liquid salt nuclear reactor is proposed:

- on the pairs of pipelines of the cooling coolant to establish coaxially and with a clearance the retarder rods having above and below the holes for the natural circulation of the cooled liquid salt fuel-containing composition;

- in the chamber of the active zone, select the outer annular region in which pairs of pipelines of the cooling coolant to install with a large step;

- to equip the fuel processing system with at least one nuclear-safe tank for receiving a liquid-salt fuel composition and transferring it for processing and at least one nuclear-safe tank for receiving a processed liquid-salt fuel composition and filling it with an active zone chamber;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium - gaseous medium, and a circulation pump for the liquid-medium cooling medium, and equipment for the circulation circuit of the gaseous medium, which includes the liquid-medium cooling medium - ”, Gas turbine generator and compressor;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes the heat-exchanger "liquid salt cooling medium - steam-water medium" and a circulation pump for the liquid-salt medium, and equipment for the circulation circuit of the steam-water medium, which includes the heat-exchange medium, heat-medium ”, Steam turbine generator and feed pump;

- to equip the reactor with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor;

- to equip the reactor with equipment for cooling the reactor with a steam-water cooling coolant, which includes a steam turbine generator and a feed pump;

- equip the reactor with a partition that forms the central chamber of the active zone and the peripheral chamber of the nuclear fuel reproduction zone, provide a pipe connected to the nozzle on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, for connecting to the filling equipment of the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant located at the bottom of the chamber of the reproduction zone with the nozzle on the reactor vessel, designed to connect Nia equipment supply of helium gas collection and treatment system, and at least one compensator safe nuclear thermal expansions Molten salt feedstock composition, coupled with horse blanket and fitted with a nozzle chamber for connecting to the gas discharge system and purification by level;

- equip the fuel processing system with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank for receiving a liquid salt raw composition and transferring it for processing and at least one nuclear-safe tank for receiving a processed liquid salt raw composition and filling it with the camera reproduction zone.

The invention is illustrated by drawings, where figure 1, 3, 5-9 shows a possible design of a liquid-salt nuclear reactor with thermal neutrons, equipped with equipment of a fuel processing system.

In figure 1, 3, 5-9 the following notation:

1 - lateral neutron reflector, 2 - upper end neutron reflector, 3 - upper tube sheet, 4 - external coolant pipe, 5 - internal coolant pipe, 6 - inlet pipe for coolant, 7 - outlet pipe for coolant, 8 - gas turbine generator 9 - dispersant located at the bottom of the chamber of the active zone, 10 - dispersant at the bottom of the chamber of the reproduction zone, 11 (1) -11 (4) - freezing valves, 12 (1) -12 (4) - shut-off valves, 13 - chamber core, 14 - zone camera in nuclear fuel production, 15 - compressor, 16 - reactor vessel, 17 - lower end neutron reflector, 18 - lower tube sheet, 19 - steam turbine generator, 20 - dispersant nozzle located at the bottom of the core chamber, 21 - dispersant nozzle located at the bottom of the zone chamber reproduction, 22 - filling pipe — emptying the chamber of the active zone, 23 — filling pipe — emptying the camera of the reproduction zone, 24 — pipe of the expansion joint for thermal expansion of the liquid-salt fuel composition, 25 — pipe of the compensator for thermal p of expansions of the liquid-salt raw material composition, 26 — a baffle, 27 — a feed pump, 28 — a fuel processing system, 29 — a gas removal and purification system, 30 — a moderator rod, 31 — a reactor power control rod, 32 — a liquid-salt cooling coolant-gaseous coolant heat exchanger ", 33 - heat exchanger" liquid salt cooling medium - steam-water medium ", 34 - pipeline dispersant located at the bottom of the chamber of the active zone, 35 - pipeline dispersant located at the bottom of the chamber zone is reproduced wa, 37 - filling pipeline — emptying the chamber of the active zone, 38 — filling pipeline — emptying the chamber of the reproduction zone, 39 (1) -39 (2) - level gauges, 40 — circulation pump of a liquid-salt cooling coolant, 41 — nuclear-safe expansion joint compensator liquid-salt fuel composition, 42 - nuclear-safe expansion joints for thermal expansion of the liquid-salt raw material composition, 43 (1) -43 (2) - nuclear-safe reservoirs of the liquid-salt fuel composition, 44 (1) -44 (2) - nuclear-safe reservoirs of the liquid-salt raw material composition ii.

The composition of a liquid-salt thermal neutron reactor includes:

Equipment for heat removal, power generation, reactor power control system, gas removal and purification system 29 and fuel processing system 28. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 pipes of the cooling fluid and containing a core 13 and the moderator rods 30 located therein. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipes, sealed in the holes of the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of the cooling medium in external 4, plugged at the bottom of the pipeline. Pipeline 37, lowered to the bottom of the core chamber 13, connected to a pipe 22 on the reactor housing 16, intended for connection to the core filling chamber equipment with a liquid salt fuel composition and emptying. A pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29. At least one nuclear-safe compensator 41 for thermal expansions of the liquid salt fuel composition connected to the top of the core 13 and provided with a pipe 24 for connection to the gas removal and purification system 29 and the level gauge 39 (1).

In addition, the composition of the liquid-salt nuclear reactor includes not shown in the drawings all electric heaters and thermal insulation of the housing 16 and other equipment.

In special cases, the execution of a liquid-salt nuclear reactor may include:

Installed coaxially and with a clearance on the pairs of pipelines of the cooling coolant, retarder rods 30 having holes at the top and bottom for the natural circulation of the cooled liquid salt fuel-containing composition. The chamber 13 of the active zone with a distinguished external annular region in which pairs of pipelines of the cooling coolant are installed with a large pitch. The fuel processing system 28 is equipped with at least one nuclear-safe tank 43 (1) for receiving a liquid-salt fuel composition and transfer for processing and at least one nuclear-safe tank 43 (2) for receiving a processed liquid-salt fuel composition and filling it with the camera 13 of the active zone. Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", Gas turbine generator 8 and compressor 15. Equipment for cooling the reactor with liquid-salt cooling t a carrier, which includes a heat exchanger 33 "liquid-salt cooling medium - a steam-water coolant" and a circulation pump 40 of a liquid-salt cooling medium, and equipment for the circulation circuit of a steam-water medium, which includes a heat exchanger 33 "a liquid-salt cooling medium - a steam-water medium, 19 steam turbine pump 27. Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 compressor 15. The cooling equipment for cooling the coolant steam-water reactor, which includes steam turbine generator 19 and the feed pump 27. The partition 26, which forms a central chamber 13 of the core and a peripheral fuel chamber 14 of the blanket. Pipeline 38 lowered to the bottom of the chamber 14 of the reproduction zone, connected to the pipe 23 on the reactor housing 16, designed to be connected to the filling equipment of the chamber 14 of the reproduction zone with a liquid-salt raw material composition and emptying. A pipeline 35 connecting the disperser 10 located at the bottom of the chamber 14 of the reproduction zone with a nozzle 21 on the reactor housing 16, designed to be connected to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe liquid-salt thermal expansion joint 42 a raw material composition connected to the top of the chamber 14 of the reproduction zone and equipped with a pipe 25 for connection with a gas removal and purification system and a level gauge 39 (2). A fuel processing system 28 equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank 44 (1) for receiving a liquid salt raw material composition and transferring it for processing and at least one nuclear-safe a reservoir 44 (2) for receiving the processed liquid salt raw material composition and filling the chamber 14 of the reproduction zone with it.

In addition, the composition of the liquid salt reactor may include: Lower 17 and upper 2 end and side 1 neutron reflectors. The rods 31 control the power of the reactor. Freezing valves 11 (1) -11 (4). Shut-off valves 12 (1) -12 (4).

The equipment for heat removal and power generation is designed to use the heat generated in the reactor. The equipment of the reactor power control system is designed to control its reactivity. The equipment of the gas removal and purification system 29 is designed to collect gaseous fission products by sparging helium with a liquid salt fuel composition, purifying them from impurities and disposing. Any other inert gas may be used for sparging. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 coolant coolant pipes, is designed to accommodate the core chamber 13 with internal 5 and external 4 coolant pipes and retarder rods 30 located therein. The direction of the entrance of the cooling fluid into the reactor vessel 16 and the exit from the reactor vessel 16 can be changed by interchanging the inlet 6 and outlet 7 pipes. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipelines, sealed along the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of coolant into external 4, plugged at the bottom of the pipeline, are designed for the necessary distribution of the cooling fluid along the cross section of the reactor. The pipe 22 on the reactor housing 16 and the pipe 37 connected to it, lowered to the bottom of the chamber 13 of the active zone, are intended to be connected to the filling equipment of the chamber 13 of the active zone with a liquid-salt fuel composition and emptying. A pipe 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16 for connecting to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe expansion joint 41 liquid-salt fuel composition, connected to the top of the chamber 13 of the active zone and equipped with a pipe 24 for connection with the system 29 removal and purification of gases and the level gauge 39 (1), are designed to remove gaseous products from the chamber 13 of the active zone Jelenia nuclear fuel. The level gauge 39 (1) is intended for monitoring and measuring the level of the fuel composition. In addition, at least one nuclear-safe compensator 41 for thermal expansions of the liquid-salt fuel composition connected to the top of the core 13 is designed to eliminate the possibility of gas cavities at the top of the core 13 and thereby keep the core geometry unchanged when the reactor is tilted .

Not shown in the drawings, electric heaters and thermal insulation are designed to heat the housing 16 and other equipment to temperatures higher than the melting temperature of the liquid salt compositions and reduce heat loss.

The moderator rods 30, mounted coaxially and with a gap on the pairs of cooling coolant pipelines and having holes at the top and bottom, are designed to slow down neutrons to thermal energy and ensure natural circulation of the cooled liquid-salt fuel-containing composition in the reactor.

The outer annular region in the chamber 13 of the active zone, in which pairs of coolant coolant pipelines are installed in large increments, is intended to form a secondary fuel reproduction zone by reducing the volume fraction of the moderator in it and increasing the volume fraction of the liquid salt fuel composition. In the thus selected region of the active zone, the reproduction of secondary nuclear fuel will proceed more intensively.

A fuel processing system 28 equipped with at least one nuclear-safe tank 43 (1) for receiving a liquid salt fuel composition and transferring it for processing and at least one nuclear-safe tank 43 (2) for receiving a processed liquid salt fuel composition and filling the chamber 13 of the active zone with it, is intended for discrete processing of a liquid salt fuel composition in order to separate from it the accumulated secondary fuel and fission products of nuclear fuel, which are neutron absorbers, eytronnymi poisons. The performance of the system 28 depends on the processing discreteness.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", A gas turbine generator 8 and compressor 15, are designed to remove heat from the reactor and to produce electric energy.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 33 "liquid-salt cooling medium - steam-water medium" and a salt-water circulation pump 40, and equipment for a steam-water medium circulation circuit, which includes a heat-exchanger 33 "liquid-salt cooling medium - a steam-water medium A steam turbine generator 19 and a feed pump 27 are also provided for removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 and compressor 15, is designed to implement the third option of removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a steam-water cooling coolant, which includes a steam turbine generator 19 and a feed pump 27, is designed to implement the fourth variant of heat removal from the reactor and the production of electricity.

The partition 26, forming the Central chamber 13 of the active zone and the peripheral chamber 14 of the zone of reproduction of nuclear fuel, is intended for the spatial separation of the processes of fission of nuclear fuel and the production of secondary nuclear fuel. Pipeline 38, which is lowered to the bottom of the chamber 14 of the reproduction zone, and the pipe 23 connected to it on the reactor housing 16 are designed to fill the chamber 14 of the reproduction zone with a liquid-salt raw material composition and emptying it. A pipeline 35 connecting the disperser 10 located at the bottom of the chamber 14 of the reproduction zone with a nozzle 21 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe liquid-salt thermal expansion joint 42 raw material composition, connected to the top of the chamber 14 of the reproduction zone and equipped with a nozzle 25 for connection to the exhaust system and gas purification, are designed to remove gaseous fission products from the chamber 14 of the reproduction zone production. The level gauge 39 (2) is designed to control and measure the level of the raw material composition. In addition, at least one nuclear-safe compensator 42 for thermal expansions of the liquid salt raw material composition is designed to exclude the possibility of gas cavities at the top of the core 14 and thereby keep the geometry of the reproduction zone unchanged when the reactor is tilted.

A fuel processing system 28 equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank 44 (1) for receiving a liquid salt raw material composition, aging and processing, and at least one nuclear -safe tank 44 (2) for receiving the processed liquid-salt raw material composition and filling the chamber 14 of the reproduction zone with it, is intended for discrete processing of the liquid salt raw material composition in order to isolate the accumulated from it of secondary fuel and nuclear fuel fission products which are neutron absorbers, neutron poisons. The performance of the system 28 depends on the processing discreteness. Continuous processing of fuel-containing compositions is also possible, but it is associated with a decrease in safety and complication of the technological scheme for the continuous selection of liquid-salt fuel-containing compositions from a working reactor and their return to a working reactor.

The lower 17 and upper 2 end and side 1 neutron reflectors are designed to reduce neutron leakage from the core. The power control rods 31 are for controlling the reactivity of the reactor.

Freezing valves 11 (1) -11 (4) are designed to seal the chamber 13 of the active zone and the chamber 14 of the reproduction zone. Shut-off valves 12 (1) -12 (4) are intended for connection with the equipment of the fuel processing system 28 or a gas station.

Pipes connecting the reactor housing 16 to the operating systems must be installed on the housing 16 above the level of the liquid salt fuel composition in at least one expansion joint 41 of the thermal expansion of the fuel composition and above the level of the liquid salt raw composition in at least one expansion joint 42 thermal expansions of the raw material composition so that in case of a defect in any of the nozzles, the fuel and raw material composition could not leak from the chamber 13 of the active zone and the chamber 14 of the reproduction zone.

A liquid salt nuclear reactor as part of a nuclear power plant or transport installation operates as follows.

Power is supplied to the electric heaters of the housing 16, nozzles 22, 23, freezing valves 11 (1) -11 (4), shut-off valves 12 (1) -12 (4), pipelines connecting the reactor with the fuel processing system 28, nuclear-safe tanks 43 (1) and 43 (2), 44 (1) and 44 (2) and other equipment of the system 28, the circulation pump 40 for the liquid salt cooling coolant, the heat exchanger 32 for the “liquid salt cooling coolant - gaseous coolant”, pipelines and other circulating equipment liquid salt coolant I am. The equipment is warmed up to the required temperature exceeding the temperature of the liquid-salt medium in it. Fill the circulation loop of the liquid salt coolant. Turn on the circulation pump 40 and pump the liquid salt cooling coolant through the reactor. From the nuclear-safe tank 44 (2) through the shut-off valve 12 (4), the freezing valve 11 (4) and the pipe 23 fill the chamber 14 of the reproduction zone with a liquid-salt feed composition according to the readings of the level gauge 39 (2) in the nuclear-safe compensator 42 of thermal expansion of the liquid-salt raw material composition. The shut-off valve 12 (4) is closed, the electric heater of the freezing valve 11 (4) is turned off, cooling is brought to it and the valve is frozen. From the nuclear-safe tank 43 (2) through the shut-off valve 12 (2), the freezing valve 11 (2) and the nozzle 22 fill the chamber 13 of the active zone with a liquid-salt fuel composition according to the readings of the level gauge 39 (1) in the nuclear-safe compensator 41 of thermal expansion of the liquid-salt fuel composition. The shut-off valve 12 (2) is closed and cooling is supplied to the freezing valve 11 (2). By means of control rods 31, the reactor is brought to the required power level. The lower 17 and upper 2 end and side 1 neutron reflectors will reduce neutron leakage outside the core 13, and the moderator rods 30 will provide the neutron thermal spectrum in it. The reactor will run on thermal neutrons. In the chamber 13 of the active zone, in the space between the moderator rods 30 and in the gaps between the moderator rods 30 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt fuel composition will be established. In the chamber 14 of the reproduction zone, in the space between the moderator rods 30 and in the gaps between the moderator rods 30 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt raw material composition will be established.

Turn on the compressor 15 and pump the gaseous coolant in the circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling coolant will transfer heat in the heat exchanger 32 to the gaseous coolant. The gaseous coolant will spend the received energy in the gas turbine generator 8 to generate electricity.

When the heat exchanger 32 "liquid salt cooling medium - gaseous liquid medium" is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

To remove from the chamber 13 of the active zone and the chamber 14 of the zone of reproduction of gaseous fission products through the nozzles 20 and 21 and dispersants 9 and 10, helium is supplied to them from the gas removal and purification system 29. Gaseous fission products released together with helium into the compensation chamber of the nuclear-safe expansion joint 41 of the thermal expansion of the liquid salt fuel composition and into the compensation chamber of the nuclear-safe expansion joint 42 of the thermal expansion of the liquid salt feed composition are pumped into the equipment of system 29, where they are cleaned of impurities and disposed of.

In order to process the fuel composition, the reactor is stopped, the freezing valves 11 (1) and 11 (2) are stopped, heated to a temperature higher than the melting temperature of the fuel composition, the shut-off valve 12 (1) is opened, and the fuel composition is drained from the core chamber 13 into nuclear safe tank 43 (1) of the fuel processing system 28. Close the shut-off valve 12 (1) and freeze the valve 11 (1). The shut-off valve 12 (2) is opened and the core chamber 13 is filled from the nuclear-safe tank 43 (2) with the previously processed fuel composition contained therein. Close the shut-off valve 12 (2) and freeze the valve 11 (2). They launch the reactor into operation and bring it to the required power level. The fuel composition poured into a nuclear-safe tank 43 (1) is processed in the equipment of the system 28 and cleaned of fission fragments and accumulated secondary fuel is collected in a nuclear-safe tank 43 (2).

In order to process the raw material composition, stop the reactor, stop the freezing valves 11 (3) and 11 (4), stop heating them to a temperature higher than the melting temperature of the raw material composition, open the shut-off valve 12 (3) and drain the raw composition from the chamber 14 of the reproduction zone into nuclear safe tank 44 (1) of the fuel processing system 28. Close the shut-off valve 12 (3) and freeze the valve 11 (3). Open the shut-off valve 12 (4) and fill the chamber 14 of the reproduction zone from the nuclear-safe tank 44 (2) with the previously processed raw material composition therein. Close the shut-off valve 12 (4) and freeze the valve 11 (4). They launch the reactor into operation and bring it to the required power level. The raw material composition, poured into a nuclear-safe tank 44 (1), is processed in the equipment of the system 28 and purified from fission fragments and accumulated secondary fuel is collected in a nuclear-safe tank 44 (2).

Another option is the heat removal from the reactor. The feed pump 27 is turned on and the steam-water coolant is pumped in its circulation circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling medium transfers heat in the heat exchanger 33 to the steam-water medium. Steam-water coolant spends the received energy in the steam turbine 19 to generate electricity.

When the heat exchanger 33 “liquid salt cooling medium - steam-water medium” is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

A third option is the heat removal from the reactor. The compressor 15 is turned on and the gaseous cooling medium is pumped through the reactor. The reactor is brought to the required power level. The gaseous cooling medium heated in the core and in the reproduction zone will spend the energy received in the gas turbine generator 8 to generate electricity.

A fourth variant of heat removal from the reactor is possible. The feed pump 27 is turned on and the steam-water coolant is pumped through the reactor. The reactor is brought to the required power level. The superheated steam obtained in the active zone and the reproduction zone will spend the received energy in the steam turbine generator 19 for the production of electricity.

When the steam turbine generator 19 is located above the reactor, the process of natural circulation of the steam-water coolant is established in the circulation circuit of the steam-water coolant. The natural circulation of the steam-water coolant will significantly reduce the load on the feed pump 27 and increase the safety of the reactor.

The developed reactor is a reactor with liquid fuel elements in which stress states do not arise with temperature changes. Therefore, it can operate in the mode of variable loads and, at the same time, no stresses associated with thermocyclic loads occur in its design. The temperature coefficient of reactivity of this reactor is always negative. The reactor has improved controllability and reliability, since the fuel and raw liquid salt compositions do not go beyond the reactor vessel when heat is removed from it and all delayed neutrons remain in the active zone and reproduction zone. The reproduction rate of the secondary fuel of the developed thermal reactor is more than one.

During wave oscillations or take-off and landing, inclinations of a reactor operating as part of a transport installation are possible. The operation of a stationary reactor operating in a nuclear power plant may be affected by seismic vibrations. When the reactor is tilted, at least one nuclear-safe compensator 41 and at least one nuclear-safe compensator 42 will ensure that the geometry of the core and the reproduction zone of nuclear fuel remain unchanged.

An example of a specific embodiment of a liquid salt nuclear reactor. For an example of a specific implementation, a liquid-salt nuclear reactor is taken - a thermal neutron converter with a uranium-thorium fuel cycle, i.e. fissile material is, for example, uranium-235, the raw material will be thorium-232, and reproducible nuclear fuel is uranium-233. The reproduction coefficient of the reactor will be more than one. As the fuel salt composition, a mixture of fluoride salts, for example 71.772 ⁷ LiF-16.0 BeF ₂ -12.0ThF ₄ -0.228UF _4, can be selected. As a liquid-salt coolant, a eutectic mixture of 92.0NaBF ₄ -8.0NaF, which has a lower melting point, can be selected. The composition of the liquid salt raw material composition can be determined by calculation and experimentally. As the main structural material, a Hastelloy-N alloy or a domestic alloy with similar properties can be selected. The molar composition of the Hastelloy-N alloy,%: Ni 66.0; Mo 17.0; Cr 7.0; Fe 5.0.

The technical result of the invention is obtained, a safe liquid-salt thermal neutron nuclear reactor is developed with a reliable body and a simple and reliable heat removal system without leaving the liquid-salt fuel composition and the liquid-salt raw material composition from the reactor vessel.

A similar design can have a thermal neutron liquid metal fuel reactor with a reliable body and a simple and reliable heat removal system without leaving the liquid metal fuel composition and the liquid metal raw material composition from the reactor vessel.

Known fast sodium-cooled reactor BN-600 (Usynin GB, Kusmartsev EV, "Fast neutron reactors", Publishing house "Energoatomizdat", Moscow, 1985). The active zone of the BN-600 reactor is composed of hexagonal cassettes consisting of rod fuel elements (fuel elements).

The main disadvantages of the known device include:

- the complexity of the design of the rod fuel rods;

- the inability to remove from the fuel rods gaseous fission products. For this reason, by the end of the campaign, in each fuel rod, the excess pressure of gaseous fission products is calculated to increase to 4 MPa;

- excessive unnecessary complexity of the design of the reactor BN-600. Near the reactor core, three circulating pumps and six “sodium-sodium” heat exchangers that are not repairable are immersed in molten activated sodium. This equipment has nothing to do with the core operation;

- low reliability of the thermal circuit. At nuclear power plants with a BN-600 reactor, there is a constant threat of dangerous contact of molten sodium of the second circuit with water.

The closest in technical essence to the claimed liquid salt nuclear reactor (options) is a liquid salt thermal neutron multiplier reactor (MSBR-1000) (Blinkin V.L., Novikov V.M. "Liquid salt nuclear reactors", M .: Atomizdat, 1978 )

The known device is a reactor with a three-circuit heat removal system. The fuel liquid salt composition circulates through the reactor vessel in the primary circuit. The generated heat is transferred from the liquid salt fuel composition in the heat exchanger to the secondary salt liquid cooling coolant. The liquid salt coolant transfers heat to the steam generator. The thermal energy of the resulting superheated steam is converted into electric energy in a steam turbine generator.

The reactor is equipped with equipment for a reactor power control system, a gas removal and purification system.

The main disadvantages of MSBR include:

- a large amount of fuel is located outside the reactor vessel, in pipelines and other equipment of the circulation circuit of the liquid salt fuel composition;

- the complexity of the design of the heat removal system from the reactor;

- liquid salt fuel composition is supplied to the reactor vessel from below. If a defect occurs in the weld connecting the inlet to the reactor vessel, the liquid-salt fuel composition may leak out of the reactor vessel;

- when the fuel is circulated through the reactor, a part of the delayed neutrons leaves the active zone with the fuel flow, therefore, the reactivity of the reactor with circulating fuel is less than the reactivity of the reactor with fuel not leaving the casing.

The technical result of the invention is to develop a safe liquid salt fast neutron reactor equipped with fuel processing equipment with a reliable body, a simple and reliable heat removal system that can be operated as part of a nuclear power plant and a transport power plant.

To achieve a technical result in a liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, a gas removal and purification system, and a fuel processing system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains a core camera, it is proposed:

- install the lower and upper tube sheets above the active zone chamber with matching holes for cooling coolant pipelines, sealed in the holes of the tube sheets and lowered into the core chamber by “pipe in pipe” pairs, the inner pipe is installed with a clearance for the passage of coolant in an external, muffled down the pipeline;

- the reactor is equipped with a pipe, lowered to the bottom of the core of the core, connected to a pipe on the reactor vessel, designed to be connected to the filling equipment of the core of the core with a liquid salt fuel composition and emptying;

- to provide the reactor with a pipeline connecting the dispersant located at the bottom of the active chamber with a nozzle on the reactor vessel designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition, connected with the top of the core of the core and equipped with a pipe for connecting to a gas removal and purification system and a level gauge.

In special cases, the execution of a liquid salt nuclear reactor is proposed:

- on the pairs of pipelines of the cooling coolant to establish coaxially and with a clearance pipelines having above and below the holes for the natural circulation of the cooled liquid salt fuel-containing composition;

- in the chamber of the active zone, select the outer annular region in which pairs of pipelines of the cooling coolant to install with a large step;

- to equip the fuel processing system with at least one nuclear-safe tank for receiving a liquid-salt fuel composition and transferring it for processing and at least one nuclear-safe tank for receiving a processed liquid-salt fuel composition and filling it with an active zone chamber;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium - gaseous medium, and a circulation pump for the liquid-medium cooling medium, and equipment for the circulation circuit of the gaseous medium, which includes the liquid-medium cooling medium - ”, Gas turbine generator and compressor;

- to equip the reactor with equipment for cooling the reactor with a liquid-salt cooling medium, which includes the heat-exchanger "liquid salt cooling medium - steam-water medium" and a circulation pump for the liquid-salt medium, and equipment for the circulation circuit of the steam-water medium, which includes the heat-exchange medium, heat-medium ”, Steam turbine generator and feed pump;

- to equip the reactor with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor;

- equip the reactor with a partition that forms the central chamber of the active zone and the peripheral chamber of the nuclear fuel reproduction zone, provide a pipe connected to the nozzle on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, for connecting to the filling equipment of the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant located at the bottom of the chamber of the reproduction zone with the nozzle on the reactor vessel, designed to connect Nia equipment supply of helium gas collection and treatment system, and at least one compensator safe nuclear thermal expansions Molten salt feedstock composition, coupled with horse blanket and fitted with a nozzle chamber for connecting to the gas discharge system and purification by level;

- equip the fuel processing system with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank for receiving a liquid salt raw composition and transferring it for processing and at least one nuclear-safe tank for receiving a processed liquid salt raw composition and filling it with the camera reproduction zone.

The invention is illustrated by drawings, where figure 2, 4-9 presents a possible design of a liquid salt nuclear fast neutron reactor equipped with fuel processing system equipment.

In figure 2, 4-9 adopted the following notation:

1 - lateral neutron reflector, 2 - upper end neutron reflector, 3 - upper tube sheet, 4 - external coolant pipe, 5 - internal coolant pipe, 6 - inlet pipe for coolant, 7 - outlet pipe for coolant, 8 - gas turbine generator 9 - dispersant located at the bottom of the chamber of the active zone, 10 - dispersant at the bottom of the chamber of the reproduction zone, 11 (1) -11 (4) - freezing valves, 12 (1) -12 (4) - shut-off valves, 13 - chamber core, 14 - zone camera in nuclear fuel production, 15 - compressor, 16 - reactor vessel, 17 - lower end neutron reflector, 18 - lower tube sheet, 19 - steam turbine generator, 20 - dispersant nozzle located at the bottom of the core chamber, 21 - dispersant nozzle located at the bottom of the zone chamber reproduction, 22 - filling nozzle - emptying the chamber of the active zone, 23 - filling nozzle - emptying the chamber of the reproduction zone, 24 - nozzle of the expansion joint for thermal expansion of the liquid-salt fuel composition, 25 - nozzle of the compensator for thermal extensions of the liquid-salt raw material composition, 26 — a baffle, 27 — a feed pump, 28 — a fuel processing system, 29 — a gas removal and purification system, 31 — a reactor power control rod, 32 — a “liquid-salt cooling medium – gaseous medium” heat exchanger, 33 —a heat exchanger “Liquid-salt cooling medium - steam-water medium”, 34 — dispersant pipe located at the bottom of the core chamber, 35 — dispersant pipe located at the bottom of the reproduction zone chamber, 36 — pipeline for e circulation of the cooled liquid-salt fuel-containing composition, 37 - filling pipeline — emptying the core chamber, 38 — filling pipeline — emptying the chamber of the reproduction zone, 39 (1) -39 (2) - level gauges, 40 - circulation pump of the liquid salt cooling coolant, 41 - nuclear -safe compensator for thermal expansions of liquid-salt fuel composition, 42 - nuclear-safe compensator for thermal expansions of liquid-salt raw material composition, 43 (1) -43 (2) - nuclear-safe tanks for liquid-salt fuel com ozitsii, 44 (1) -44 (2) - nuclear safe tanks Molten salt feedstock composition.

The composition of a liquid-salt fast neutron reactor includes:

Equipment for heat removal, power generation, reactor power control system, gas removal and purification system 29 and fuel processing system 28. The housing 16 of the reactor, equipped with at least one inlet 6 and one outlet 7 pipes of the cooling fluid and containing a chamber 13 of the active zone. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipes, sealed in the holes of the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of the cooling medium in external 4, plugged at the bottom of the pipeline. Pipeline 37, lowered to the bottom of the core chamber 13, connected to a pipe 22 on the reactor housing 16, intended for connection to the core filling chamber equipment with a liquid salt fuel composition and emptying. A pipeline 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29. At least one nuclear-safe compensator 41 for thermal expansions of the liquid salt fuel composition connected to the top of the core 13 and provided with a pipe 24 for connection to the gas removal and purification system 29 and the level gauge 39 (1).

In addition, the composition of the liquid-salt nuclear reactor includes not shown in the drawings all electric heaters and thermal insulation of the housing 16 and other equipment.

In special cases, the execution of a liquid-salt nuclear reactor may include:

Installed coaxially and with a clearance on the pairs of pipelines of the cooling fluid, pipelines 36 having openings at the top and bottom for the natural circulation of the cooled liquid-salt fuel-containing composition. The chamber 13 of the active zone with a distinguished external annular region in which pairs of pipelines of the cooling coolant are installed with a large pitch. The fuel processing system 28 is equipped with at least one nuclear-safe tank 43 (1) for receiving a liquid-salt fuel composition and transfer for processing and at least one nuclear-safe tank 43 (2) for receiving a processed liquid-salt fuel composition and filling it with the camera 13 of the active zone. Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", Gas turbine generator 8 and compressor 15. Equipment for cooling the reactor with liquid-salt cooling t a carrier, which includes a heat exchanger 33 "liquid-salt cooling medium - a steam-water coolant" and a circulation pump 40 of a liquid-salt cooling medium, and equipment for the circulation circuit of a steam-water medium, which includes a heat exchanger 33 "a liquid-salt cooling medium - a steam-water medium, 19 steam turbine pump 27. Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 compressor 15. The baffle 26 forming the central chamber 13 of the core and a peripheral fuel chamber 14 of the blanket. Pipeline 38 lowered to the bottom of the chamber 14 of the reproduction zone, connected to the pipe 23 on the reactor housing 16, designed to be connected to the filling equipment of the chamber 14 of the reproduction zone with a liquid-salt raw material composition and emptying. A pipeline 35 connecting the disperser 10 located at the bottom of the chamber 14 of the reproduction zone with a nozzle 21 on the reactor housing 16, designed to be connected to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe liquid-salt thermal expansion joint 42 a raw material composition connected to the top of the chamber 14 of the reproduction zone and equipped with a pipe 25 for connection with a gas removal and purification system and a level gauge 39 (2). A fuel processing system 28 equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank 44 (1) for receiving a liquid salt raw material composition and transferring it for processing and at least one nuclear-safe a reservoir 44 (2) for receiving the processed liquid salt raw material composition and filling the chamber 14 of the reproduction zone with it.

In addition, the composition of the liquid salt reactor may include: Lower 17 and upper 2 end and side 1 neutron reflectors. The rods 31 control the power of the reactor. Freezing valves 11 (1) -11 (4). Shut-off valves 12 (1) -12 (4).

The equipment for heat removal and power generation is designed to use the heat generated in the reactor. The equipment of the reactor power control system is designed to control its reactivity. The equipment of the gas removal and purification system 29 is designed to collect gaseous fission products by sparging helium with a liquid salt fuel composition, purifying them from impurities and disposing. Any other inert gas may be used for sparging. The reactor vessel 16, equipped with at least one inlet 6 and one outlet 7 coolant coolant pipes, is designed to accommodate the core chamber 13 with the internal 5 and external 4 coolant coolant pipes and pipelines 36. The direction of the coolant coolant inlet 16 of the reactor and exit from the reactor vessel 16 can be changed by interchanging the inlet 6 and outlet 7 nozzles. The lower 18 and upper 3 tube sheets installed above the chamber 13 of the active zone with matching holes for the coolant pipelines, sealed along the tube sheets and lowered into the chamber 13 of the core in pairs “pipe in pipe”, the inner 5 pipe is installed with a clearance for passage of coolant into external 4, plugged at the bottom of the pipeline, are designed for the necessary distribution of the cooling fluid along the cross section of the reactor. The pipe 22 on the reactor housing 16 and the pipe 37 connected to it, lowered to the bottom of the chamber 13 of the active zone, are intended to be connected to the filling equipment of the chamber 13 of the active zone with a liquid-salt fuel composition and emptying. A pipe 34 connecting the disperser 9 located at the bottom of the core chamber 13 with a nozzle 20 on the reactor housing 16 for connecting to helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe expansion joint 41 liquid-salt fuel composition, connected to the top of the chamber 13 of the active zone and equipped with a pipe 24 for connection with the system 29 removal and purification of gases and the level gauge 39 (1), are designed to remove gaseous products from the chamber 13 of the active zone Jelenia nuclear fuel. The level gauge 39 (1) is intended for monitoring and measuring the level of the fuel composition. In addition, at least one nuclear-safe expansion joint 41 thermal expansion of the liquid salt fuel composition connected to the top of the chamber 13 of the active zone. designed to exclude the possibility of gas cavities at the top of the chamber 13 of the active zone and thereby keep the geometry of the active zone unchanged when the reactor is tilted.

Not shown in the drawings, electric heaters and thermal insulation are designed to heat the housing 16 and other equipment to temperatures higher than the melting temperature of the liquid salt compositions and reduce heat loss.

Pipelines 36, installed coaxially and with a gap on the pairs of pipelines of the cooling fluid and having holes at the top and bottom, are designed to provide natural circulation of the cooled liquid-salt fuel-containing composition in the reactor.

The outer annular region in the chamber 13 of the active zone, in which pairs of coolant coolant pipelines are installed in large increments, is intended to form a secondary fuel reproduction zone by increasing the volume fraction of the liquid salt fuel composition in it. In the area thus identified, the reproduction of secondary nuclear fuel will proceed more intensively.

A fuel processing system 28 equipped with at least one nuclear-safe tank 43 (1) for receiving a liquid salt fuel composition and transferring it for processing and at least one nuclear-safe tank 43 (2) for receiving a processed liquid salt fuel composition and filling the chamber 13 of the active zone with it, is intended for discrete processing of a liquid salt fuel composition in order to separate from it the accumulated secondary fuel and fission products of nuclear fuel, which are neutron absorbers, eytronnymi poisons. The performance of system 28 will depend on the processing discreteness.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 32 "liquid-salt cooling medium - gaseous heat carrier" and a circulation pump 40 of an liquid-salt cooling medium, and equipment for the circulation circuit of a gaseous liquid medium, which includes a heat exchanger 32 "liquid-salt cooling medium - a gaseous ", A gas turbine generator 8 and compressor 15, are designed to remove heat from the reactor and to produce electric energy.

Equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger 33 "liquid-salt cooling medium - steam-water medium" and a salt-water circulation pump 40, and equipment for a steam-water medium circulation circuit, which includes a heat-exchanger 33 "liquid-salt cooling medium - a steam-water medium A steam turbine generator 19 and a feed pump 27 are also provided for removing heat from the reactor and generating electricity.

Equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator 8 and compressor 15, is designed to implement the third option of removing heat from the reactor and generating electricity.

The partition 26, forming the Central chamber 13 of the active zone and the peripheral chamber 14 of the zone of reproduction of nuclear fuel, is intended for the spatial separation of the processes of fission of nuclear fuel and the production of secondary nuclear fuel. Pipeline 38, which is lowered to the bottom of the chamber 14 of the reproduction zone, and the pipe 23 connected to it on the reactor housing 16 are designed to fill the chamber 14 of the reproduction zone with a liquid-salt raw material composition and emptying it. A pipeline 35 connecting the disperser 10 located at the bottom of the chamber 14 of the reproduction zone with a nozzle 21 on the reactor housing 16, intended for connection with helium supply equipment from the gas removal and purification system 29, and at least one nuclear-safe liquid-salt thermal expansion joint 42 raw material composition, connected to the top of the chamber 14 of the reproduction zone and equipped with a nozzle 25 for connection to the exhaust system and gas purification, are designed to remove gaseous fission products from the chamber 14 of the reproduction zone production. The level gauge 39 (2) is designed to control and measure the level of the raw material composition. In addition, at least one nuclear-safe compensator 42 for thermal expansions of the liquid salt raw material composition is designed to exclude the possibility of gas cavities at the top of the core 14 and thereby keep the geometry of the reproduction zone unchanged when the reactor is tilted.

A fuel processing system 28 equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank 44 (1) for receiving a liquid salt raw material composition, aging and processing, and at least one nuclear -safe tank 44 (2) for receiving the processed liquid-salt raw material composition and filling the chamber 14 of the reproduction zone with it, is intended for discrete processing of the liquid salt raw material composition in order to isolate the accumulated from it of secondary fuel and nuclear fuel fission products which are neutron absorbers, neutron poisons. The performance of system 28 will depend on the processing discreteness. Continuous processing of fuel-containing compositions is also possible, but it is associated with a decrease in safety and complication of the technological scheme for the continuous selection of liquid-salt fuel-containing compositions from a working reactor and their return to a working reactor.

The lower 17 and upper 2 end and side 1 neutron reflectors are designed to reduce neutron leakage from the core. The power control rods 31 are for controlling the reactivity of the reactor.

Freezing valves 11 (1) -11 (4) are designed to seal the chamber 13 of the active zone and the chamber 14 of the reproduction zone. Shut-off valves 12 (1) -12 (4) are intended for connection with the equipment of the fuel processing system 28 or a gas station.

Pipes connecting the reactor housing 16 to the operating systems must be installed on the housing 16 above the level of the liquid salt fuel composition in at least one expansion joint 41 of the thermal expansion of the fuel composition and above the level of the liquid salt raw composition in at least one expansion joint 42 thermal expansions of the raw material composition so that in case of a defect in any of the nozzles, the fuel and raw material composition could not leak from the chamber 13 of the active zone and the chamber 14 of the reproduction zone.

A liquid salt fast-neutron reactor in a nuclear power plant or transport installation operates as follows.

Power is supplied to the electric heaters of the housing 16, nozzles 22, 23, freezing valves 11 (1) -11 (4), shut-off valves 12 (1) -12 (4), pipelines connecting the reactor with the fuel processing system 28, nuclear-safe tanks 43 (1) and 43 (2), 44 (1) and 44 (2) and other equipment of the system 28, the circulation pump 40 for the liquid salt cooling coolant, the heat exchanger 32 for the “liquid salt cooling coolant - gaseous coolant”, pipelines and other circulating equipment liquid salt coolant I am. The equipment is warmed up to the required temperature exceeding the temperature of the liquid-salt medium in it. Fill the circulation loop of the liquid salt coolant. Turn on the circulation pump 40 and pump the liquid salt cooling coolant through the reactor. From the nuclear-safe tank 44 (2) through the shut-off valve 12 (4), the freezing valve 11 (4) and the pipe 23 fill the chamber 14 of the reproduction zone with a liquid-salt feed composition according to the readings of the level gauge 39 (2) in the nuclear-safe compensator 42 of thermal expansion of the liquid-salt raw material composition. The shut-off valve 12 (4) is closed, the electric heater of the freezing valve 11 (4) is turned off, cooling is brought to it and the valve is frozen. From the nuclear-safe tank 43 (2) through the shut-off valve 12 (2), the freezing valve 11 (2) and the nozzle 22 fill the chamber 13 of the active zone with a liquid-salt fuel composition according to the readings of the level gauge 39 (1) in the nuclear-safe compensator 41 of thermal expansion of the liquid-salt fuel composition. The shut-off valve 12 (2) is closed and cooling is supplied to the freezing valve 11 (2). By means of control rods 31, the reactor is brought to the required power level. The lower 17 and upper 2 end and side 1 neutron reflectors will reduce neutron leakage outside the reactor. Due to the absence of a moderator, a fast neutron spectrum will be established in the reactor and it will operate on fast neutrons. In the chamber 13 of the active zone, in the space between the moderator rods 30 and in the gaps between the moderator rods 30 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt fuel composition will be established. In the chamber 14 of the reproduction zone, in the space between the moderator rods 30 and in the gaps between the moderator rods 30 and the outer surfaces of the external 4 cooling pipelines, the process of natural circulation of the liquid salt raw material composition will be established.

Turn on the compressor 15 and pump the gaseous coolant in the circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling coolant will transfer heat in the heat exchanger 32 to the gaseous coolant. The gaseous coolant will spend the received energy in the gas turbine generator 8 to generate electricity.

When the heat exchanger 32 "liquid salt cooling medium - gaseous liquid medium" is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

To remove from the chamber 13 of the active zone and the chamber 14 of the zone of reproduction of gaseous fission products through the nozzles 20 and 21 and dispersants 9 and 10, helium is supplied to them from the gas removal and purification system 29. Gaseous fission products released together with helium into the compensation chamber of the nuclear-safe expansion joint 41 of the thermal expansion of the liquid salt fuel composition and into the compensation chamber of the nuclear-safe expansion joint 42 of the thermal expansion of the liquid salt feed composition are pumped into the equipment of system 29, where they are cleaned of impurities and disposed of.

In order to process the fuel composition, the reactor is stopped, the freezing valves 11 (1) and 11 (2) are stopped, heated to a temperature higher than the melting temperature of the fuel composition, the shut-off valve 12 (1) is opened, and the fuel composition is drained from the core chamber 13 into nuclear safe tank 43 (1) of the fuel processing system 28. Close the shut-off valve 12 (1) and freeze the valve 11 (1). The shut-off valve 12 (2) is opened and the core chamber 13 is filled from the nuclear-safe tank 43 (2) with the previously processed fuel composition contained therein. Close the shut-off valve 12 (2) and freeze the valve 11 (2). They launch the reactor into operation and bring it to the required power level. The fuel composition poured into a nuclear-safe tank 43 (1) is processed in the equipment of the system 28 and cleaned of fission fragments and accumulated secondary fuel is collected in a nuclear-safe tank 43 (2).

In order to process the raw material composition, stop the reactor, stop the freezing valves 11 (3) and 11 (4), stop heating them to a temperature higher than the melting temperature of the raw material composition, open the shut-off valve 12 (3) and drain the raw composition from the chamber 14 of the reproduction zone into nuclear safe tank 44 (1) of the fuel processing system 28. Close the shut-off valve 12 (3) and freeze the valve 11 (3). Open the shut-off valve 12 (4) and fill the chamber 14 of the reproduction zone from the nuclear-safe tank 44 (2) with the previously processed raw material composition therein. Close the shut-off valve 12 (4) and freeze the valve 11 (4). They launch the reactor into operation and bring it to the required power level. The raw material composition, poured into a nuclear-safe tank 44 (1), is processed in the equipment of the system 28 and purified from fission fragments and accumulated secondary fuel is collected in a nuclear-safe tank 44 (2).

Another option is the heat removal from the reactor. The feed pump 27 is turned on and the steam-water coolant is pumped in its circulation circuit. Heated in the active zone 13 and the reproduction zone 14, the liquid salt cooling medium transfers heat in the heat exchanger 33 to the steam-water medium. Steam-water coolant spends the received energy in the steam turbine 19 to generate electricity.

When the heat exchanger 33 “liquid salt cooling medium - steam-water medium” is located above the reactor, the process of its natural circulation will be established in the circulation circuit of the liquid salt cooling medium. The natural circulation of the liquid-salt coolant will significantly reduce the load on the circulation pump 40 and increase the safety of the reactor.

A third option is the heat removal from the reactor. The compressor 15 is turned on and the gaseous cooling medium is pumped through the reactor. The reactor is brought to the required power level. The gaseous cooling medium heated in the core and in the reproduction zone will spend the energy received in the gas turbine generator 8 to generate electricity.

The developed reactor is a reactor with liquid fuel elements in which stress states do not arise with temperature changes. Therefore, it can operate in the mode of variable loads and at the same time, no stresses associated with thermocyclic loads occur in its design. The temperature coefficient of reactivity of this reactor is always negative. The reactor has improved controllability and reliability, since the fuel and raw liquid salt compositions do not go beyond the reactor vessel when heat is removed from it and all delayed neutrons remain in the active zone and reproduction zone. The secondary fuel reproduction rate of the developed fast reactor is more than one.

During wave oscillations or take-off and landing, inclinations of a reactor operating as part of a transport installation are possible. The operation of a stationary reactor operating in a nuclear power plant may be affected by seismic vibrations. When the reactor is tilted, at least one nuclear-safe compensator 41 and at least one nuclear-safe compensator 42 will ensure that the geometry of the core and the reproduction zone of nuclear fuel remain unchanged.

An example of a specific embodiment of a liquid salt nuclear reactor.

For an example of a specific implementation, a liquid-salt nuclear reactor is taken - a thermal neutron converter with a uranium-thorium fuel cycle, i.e. fissile material is, for example, uranium-235, the raw material will be thorium-232, and reproducible nuclear fuel is uranium-233. The reproduction coefficient of the reactor will be more than one. As the fuel salt composition, a mixture of fluoride salts, for example, 71.772 ⁷ LiF-16.0 BeF ₂ -12.0ThF ₄ -0.228UF _4, can be selected. As a liquid-salt coolant, a eutectic mixture of 92.0NaBF ₄ -8.0NaF, which has a lower melting point, can be selected. The composition of the liquid salt raw material composition can be determined by calculation and experimentally. As the main structural material, a Hastelloy-N alloy or a domestic alloy with similar properties can be selected. The molar composition of the Hastelloy-N alloy,%: Ni 66.0; Mo 17.0; Cr 7.0; Fe 5.0.

The technical result of the invention is obtained, a safe liquid-salt fast-neutron nuclear reactor is developed, with a reliable body and a simple and reliable heat removal system without leaving the liquid-salt fuel composition and the liquid-salt raw material composition from the reactor vessel.

A similar design may have a fast-neutron liquid metal fuel reactor with a reliable body and a simple and reliable heat removal system without leaving the liquid metal fuel composition and the liquid metal raw material composition from the reactor vessel.

List of items

one Side neutron reflector 2 Top end neutron reflector 3 Upper tube sheet four External coolant pipe 5 Internal coolant pipe 6 Coolant coolant inlet 7 Coolant Fluid Outlet 8 Gas turbine generator 9 Dispersant located at the bottom of the core chamber 10 Dispersant located at the bottom of the chamber of the reproduction zone 11 (1) -11 (4) Freezing valves 12 (1) -12 (4) Stop valves 13 Core camera fourteen Nuclear fuel reproduction area chamber fifteen Compressor 16 Reactor vessel 17 Lower end neutron reflector eighteen Lower tube sheet 19 Steam turbine generator twenty Dispersant pipe located at the bottom of the core chamber 21 Dispersant pipe located at the bottom of the chamber of the reproduction zone 22 Filling pipe - emptying the core chamber 23 Filling nozzle - emptying the chamber of the reproduction zone 24 Compensator pipe for thermal expansion of the liquid salt fuel composition 25 Compensator pipe for thermal expansion of a liquid-salt raw material composition 26 Partition 27 Feed pump 28 Fuel processing system 29th Gas exhaust and purification system thirty Retarder rod 31 Reactor power control rod 32 Heat exchanger "liquid salt cooling medium - gaseous medium" 33 Heat exchanger "liquid-salt cooling medium - steam-water medium" 34 Dispersant piping located at the bottom of the core chamber 35 Dispersant pipeline located at the bottom of the chamber of the reproduction zone 36 Pipeline for the natural circulation of a cooled liquid salt fuel-containing composition 37 Filling pipeline - emptying the core chamber 38 Filling pipeline - emptying the chamber of the reproduction area 39 (1) -39 (2) Level gauges 40 The circulation pump of the liquid salt cooling coolant 41 Nuclear-Safe Compensator for Thermal Extensions of the Liquid Salt Fuel Composition 42 Nuclear-Safe Compensator for Thermal Extensions of a Liquid-Salt Raw Material Composition 43 (1) -43 (2) Nuclear-safe reservoirs of liquid salt fuel composition 44 (1) -44 (2) Nuclear-safe reservoirs of liquid salt composition

Claims (34)

1. A liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, and a gas removal and purification system, the casing of which is equipped with at least one inlet and one outlet nozzles of a coolant and contains an active zone chamber and the moderator rods in it, characterized in that the lower and upper tube sheets with matching holes for cooling coolant pipes are installed above the core chamber e in the openings of the tube sheets and lowered into the chamber of the core in pairs "pipe in pipe", the inner pipe is installed with a clearance for the passage of the cooling fluid in the outer; plugged at the bottom of the pipeline, the reactor is equipped with a pipe down to the bottom of the core of the active zone, connected to a pipe on the reactor vessel, designed to connect to the filling equipment of the core of the core with a liquid salt fuel composition and emptying, a pipe connecting the dispersant located at the bottom of the core of the chamber with a pipe on the reactor body intended for connection with helium supply equipment from a gas removal and purification system, and at least one nuclear-safe compensator ohm of thermal expansions of the liquid salt fuel composition connected to the top of the core of the active zone and equipped with a pipe for connection to a gas removal and purification system and a level gauge. 2. The liquid salt nuclear reactor according to claim 1, characterized in that on the pairs of pipelines of the cooling coolant are installed coaxially and with a lumen of the retarder rods having holes at the top and bottom for natural circulation of the cooled liquid salt fuel-containing composition. 3. A liquid salt nuclear reactor according to any one of claims 1 and 2, characterized in that an outer annular region is distinguished in the core chamber in which pairs of coolant coolant pipelines are installed in large increments. 4. A liquid salt nuclear reactor according to any one of claims 1 and 2, characterized in that it is equipped with a partition forming a central chamber of the active zone and a peripheral chamber of the nuclear fuel reproduction zone, equipped with a pipe connected to the pipe on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, intended for connection with the equipment for filling the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, with a pipeline connecting the dispersant located at the bottom of the chamber of the reproduction zone with a nozzle on the reactor vessel intended for connection with helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt raw material composition, connected to the top of the chamber of the reproduction zone and equipped with a nozzle for connecting to the system removal and purification of gases and level gauge. 5. A liquid salt nuclear reactor according to any one of claims 1 and 2, characterized in that it is equipped with equipment for cooling the reactor with a liquid salt cooling medium, which includes a heat exchange liquid salt cooling medium, a gaseous liquid medium and a liquid salt cooling medium circulation pump, and circulation loop equipment gaseous heat carrier, which includes the heat exchanger "liquid salt cooling coolant - gaseous coolant", a gas turbine generator and pressor. 6. A liquid-salt nuclear reactor according to any one of claims 1 and 2, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger "liquid-salt cooling medium, a steam-water medium" and a circulation pump for a liquid-salt liquid cooling medium, and circulation circuit equipment steam-water coolant, which includes the heat exchanger "liquid salt cooling coolant - steam-water coolant", a steam turbine generator and feed flax pump. 7. A liquid salt nuclear reactor according to any one of claims 1 and 2, characterized in that it is equipped with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor. 8. A liquid-salt nuclear reactor according to any one of claims 1 and 2, characterized in that it is equipped with equipment for cooling the reactor with a steam-water cooling medium, which includes a steam turbine generator and a feed pump. 9. A liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, and a gas removal and purification system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains an active zone chamber the fact that the lower and upper tube sheets with matching openings for cooling coolant pipelines are sealed in the holes of the tube sheets and are omitted above the core chamber placed in the core of the core in pairs “pipe in pipe”, the inner pipe is installed with a clearance for the passage of the cooling fluid in the external pipe drowned at the bottom, the reactor is equipped with a pipe down to the bottom of the core of the core, connected to the pipe on the reactor vessel, designed to connect with equipment filling the core of the core with a liquid-salt fuel composition and emptying it with a pipe connecting the dispersant located at the bottom of the core of the core with a pipe on the reactor vessel, etc. designed to connect with helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition, connected to the top of the core of the active zone and equipped with a pipe for connecting to the gas removal and purification system and level gauge . 10. The liquid salt nuclear reactor according to claim 9, characterized in that the pairs of pipes of the cooling coolant are installed coaxially and with a lumen of pipelines having openings at the top and bottom for natural circulation of the cooled liquid salt fuel-containing composition. 11. A liquid salt nuclear reactor according to any one of claims 9 and 10, characterized in that an outer annular region is distinguished in the core chamber in which pairs of coolant coolant pipelines are installed in large increments. 12. A liquid salt nuclear reactor according to any one of claims 9 and 10, characterized in that it is equipped with a baffle forming a central chamber of the active zone and a peripheral chamber of the nuclear fuel reproduction zone, equipped with a pipe connected to the pipe on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, intended for connection with the equipment for filling the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant with a nozzle on the reactor vessel intended for connection with helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt raw material composition, connected to the top of the chamber of the reproduction zone and equipped with a nozzle for connecting to the system removal and purification of gases and level gauge. 13. A liquid salt nuclear reactor according to any one of claims 9 and 10, characterized in that it is equipped with equipment for cooling the reactor with a liquid salt cooling medium, which includes a heat exchange liquid salt cooling liquid, a gaseous liquid medium and a liquid salt cooling liquid circulation pump, and circulation loop equipment gaseous coolant, which includes a heat exchanger "liquid salt cooling coolant - gaseous coolant", a gas turbine generator and mpressor. 14. A liquid-salt nuclear reactor according to any one of claims 9 and 10, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger "liquid-salt cooling medium, a steam-water medium" and a circulation pump for a liquid-salt cooling medium, and circulation circuit equipment steam-water coolant, which includes a heat exchanger "liquid salt cooling coolant - steam-water coolant", a steam turbine generator and feed single pump. 15. A liquid-salt nuclear reactor according to any one of claims 9 and 10, characterized in that it is equipped with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor. 16. A liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, a gas removal and purification system, and a fuel processing system, the casing of which is equipped with at least one inlet and one outlet nozzles of the coolant and contains a chamber core and retarder rods located in it, characterized in that the lower and upper tube sheets with matching holes for cooling pipes are installed above the core chamber its coolant, sealed in the openings of the tube sheets and lowered into the chamber of the active zone by pairs of “pipe in pipe”, the inner pipe is installed with a clearance for the passage of the cooling coolant in the external pipe drowned at the bottom, the reactor is equipped with a pipe lowered to the bottom of the chamber of the core, connected to the pipe on the reactor vessel, designed to be connected to the equipment for filling the chamber of the active zone with a liquid salt fuel composition and emptying, by a pipe connecting downstream a core chamber a disperser with a nozzle on the reactor vessel, designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of a liquid-salt fuel composition connected to the top of the core chamber and equipped with a nozzle for connection to a gas removal and purification system and a level gauge. 17. A liquid salt nuclear reactor according to claim 16, characterized in that, on pairs of pipelines of the cooling coolant, moderator rods are installed coaxially and with a clearance, having openings at the top and bottom for natural circulation of the cooled liquid salt fuel-containing composition. 18. A liquid salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that an outer annular region is highlighted in the core chamber in which pairs of coolant coolant pipelines are installed in large increments. 19. A liquid salt nuclear reactor according to any one of claims 16 and 17, characterized in that the fuel processing system is equipped with at least one nuclear-safe tank for receiving a liquid salt fuel composition and transferring it for processing and at least one nuclear a safe reservoir for receiving the processed liquid salt fuel composition and filling the core of the core with it. 20. A liquid-salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium, a gaseous liquid medium and a circulation pump for liquid-liquid cooling medium, and circulation loop equipment gaseous coolant, which includes the heat exchanger "liquid salt cooling coolant - gaseous coolant", a gas turbine generator and mpressor. 21. The liquid salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger "liquid-salt cooling medium, a water-steam medium" and a circulation pump for a liquid-salt cooling medium, and circulation circuit equipment steam-water coolant, which includes a heat exchanger "liquid salt cooling coolant - steam-water coolant", a steam turbine generator and pita Yelnia pump. 22. The liquid salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that it is equipped with a cooling device for the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor. 23. A liquid salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that it is equipped with equipment for cooling the reactor with a steam-water cooling medium, which includes a steam turbine generator and a feed pump. 24. A liquid salt nuclear reactor according to any one of paragraphs.16 and 17, characterized in that it is equipped with a partition forming a central chamber of the active zone and a peripheral chamber of the nuclear fuel reproduction zone, equipped with a pipe connected to the pipe on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, intended for connection with the equipment for filling the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant p with a nozzle on the reactor vessel intended for connection with helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt raw material composition, connected to the top of the chamber of the reproduction zone and equipped with a nozzle for connection with gas removal and purification system and level gauge. 25. The liquid salt nuclear reactor according to paragraph 24, wherein the fuel processing system is equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank for receiving a liquid salt raw material composition and transfer for processing and, at least one nuclear-safe tank for receiving the processed liquid-salt raw material composition and filling the chamber of the reproduction zone with it. 26. A liquid salt nuclear reactor equipped with equipment for heat removal, power generation, a reactor power control system, a gas removal and purification system, and a fuel processing system, the casing of which is equipped with at least one inlet and one outlet nozzles of a cooling coolant and contains a chamber core, characterized in that the lower and upper tube sheets with matching holes for cooling coolant pipelines sealed in the opening are installed above the core chamber ia pipe gratings and “pipe in pipe” pairs lowered into the core of the core, the inner pipe is installed with a clearance for the passage of the coolant in the external pipe plugged down below, the reactor is equipped with a pipe down to the bottom of the core of the core, connected to the pipe on the reactor vessel, designed for connecting to the equipment for filling the chamber of the active zone with a liquid-salt fuel composition and emptying, a pipeline connecting the dispersant located at the bottom of the chamber of the active zone with a path a plug on the reactor vessel, designed to be connected to helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt fuel composition connected to the top of the core of the active zone and equipped with a pipe for connecting to the exhaust system and gas purification and level gauge. 27. The liquid salt nuclear reactor according to claim 26, characterized in that the pairs of pipes of the cooling coolant are installed coaxially and with clearance, pipelines having openings at the top and bottom for natural circulation of the cooled liquid salt fuel-containing composition, 28. A liquid salt nuclear reactor according to any one of claims 26 and 27, characterized in that an outer annular region is distinguished in the core chamber in which pairs of coolant coolant pipelines are installed in large increments. 29. A liquid salt nuclear reactor according to any one of claims 26 and 27, characterized in that the fuel processing system is equipped with at least one nuclear-safe tank for receiving a liquid salt fuel composition and transferring it for processing and at least one nuclear a safe reservoir for receiving the processed liquid salt fuel composition and filling the core of the core with it. 30. A liquid-salt nuclear reactor according to any one of claims 26 and 27, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchanger "liquid-salt cooling medium, a gaseous medium" and a liquid-salt cooling medium circulation pump, and circulation loop equipment gaseous coolant, which includes the heat exchanger "liquid salt cooling coolant - gaseous coolant", a gas turbine generator and mpressor. 31. A liquid-salt nuclear reactor according to any one of paragraphs.26 and 27, characterized in that it is equipped with equipment for cooling the reactor with a liquid-salt cooling medium, which includes a heat-exchange liquid-salt cooling medium and a water-water medium, and a liquid-salt cooling medium circulation pump, and circulation equipment steam-water coolant, which includes a heat exchanger "liquid salt cooling coolant - steam-water coolant", a steam turbine generator and pita Yelnia pump. 32. A liquid salt nuclear reactor according to any one of paragraphs.26 and 27, characterized in that it is equipped with equipment for cooling the reactor with a gaseous cooling medium, which includes a gas turbine generator and a compressor. 33. A liquid salt nuclear reactor according to any one of claims 26 and 27, characterized in that it is equipped with a baffle forming a central chamber of the active zone and a peripheral chamber of the nuclear fuel reproduction zone, provided with a pipe connected to the pipe on the reactor vessel, lowered to the bottom of the chamber of the reproduction zone, intended for connection with the equipment for filling the chamber of the reproduction zone with a liquid-salt raw material composition and emptying, a pipeline connecting the dispersant p with a nozzle on the reactor vessel intended for connection with helium supply equipment from the gas removal and purification system, and at least one nuclear-safe compensator for thermal expansions of the liquid-salt raw material composition, connected to the top of the chamber of the reproduction zone and equipped with a nozzle for connection with gas removal and purification system and level gauge. 34. A liquid salt nuclear reactor according to claim 33, wherein the fuel processing system is equipped with equipment for processing a liquid salt raw material composition, which includes at least one nuclear-safe tank for receiving a liquid salt raw material composition and transferring it for processing, and, at least one nuclear-safe tank for receiving the processed liquid-salt raw material composition and filling the chamber of the reproduction zone with it.

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