CN116779197A - Nuclear heating reactor with dry well and adjustable power - Google Patents

Abstract

The invention provides a nuclear heating reactor with a dry well and adjustable power, and belongs to the technical field of nuclear reactors. The problem of current nuclear heating reactor power limited is solved. The reactor comprises a reactor container, a reactor core, a dry well, control rods, heat rising partition plates, turbulence assemblies and an adjustable power heat exchange system, wherein the reactor core and the dry well are arranged inside the reactor container, normal pressure and no coolant are arranged in the dry well, the control rods are arranged in the dry well and inserted into the reactor core, the heat rising partition plates are arranged outside the dry well, a rising channel and a falling channel of the coolant are isolated through the heat rising partition plates, the coolant is flashed in the rising channel, the turbulence assemblies are arranged in each sub-channel, the adjustable power heat exchange system comprises a bus and a plurality of sub-heat exchange systems, the bus is arranged in the dry well, the sub-heat exchange systems are uniformly arranged in each sub-channel, and the sub-heat exchange systems are connected with the bus. It is mainly used for nuclear heating reactor.

Description

Nuclear heating reactor with dry well and adjustable power

Technical Field

The invention belongs to the technical field of nuclear reactors, and particularly relates to a nuclear heating reactor with a dry well and adjustable power.

Background

In recent decades, there are many designs of domestic and foreign heating reactors, such as soviet union shell type integrated natural circulation pressurized water reactor ATS-500, canada SLOW pool natural circulation pool type heating reactor, sweden Agesta, but the economical efficiency and safety are not widely accepted, and the problems of complex structure and the like exist.

The existing heat supply reactor mostly adopts natural circulation design, and natural circulation driving force and heat carrying capacity are limited, when the power of the reactor core is high, the heat generated by the reactor core is difficult to carry out by only relying on single-phase natural circulation, so the natural circulation capacity of the reactor is mostly improved by adopting a method for reducing the power of the reactor or improving the height difference of cold and hot sections in the reactor. These methods limit the power level of the reactor and limit the application requirements of the reactor on the one hand; on the other hand, the structural size of the reactor is increased, which is unfavorable for miniaturization of the reactor.

The coolant in the reactor is subjected to flash evaporation phenomenon due to pressure reduction under the condition of approaching the saturation temperature, the flash evaporation phenomenon can effectively enhance natural circulation driving force and improve the flow rate of the coolant in a first loop, but at the same time, the coolant can cause large-amplitude oscillation, which is unfavorable for the operation of the nuclear heating reactor.

The control rod of the reactor is generally inserted from the upper end enclosure of the pressure vessel, when the whole length of the reactor is longer, the length of the control rod must be longer, and a considerable part of the control rod is soaked in the coolant to be heated and irradiated, so that the risk of bending and even breaking of the control rod is increased.

Disclosure of Invention

In view of the above, the present invention aims to provide a nuclear heating reactor with a dry well and adjustable power, so as to solve the problem of power limitation of the existing nuclear heating reactor.

In order to achieve the above purpose, the present invention adopts the following technical scheme: the utility model provides a nuclear heating reactor with adjustable power of drywell, it includes reactor vessel, reactor core, drywell, control rod, heat rising baffle, vortex subassembly and adjustable power heat transfer system, reactor core and drywell set up in the reactor vessel inside, the drywell is located a certain distance department directly over the reactor core, the drywell top links to each other with reactor vessel upper portion, be ordinary pressure and no coolant in the drywell, control rod quantity is a plurality of, and a plurality of control rod sets up in the drywell and inserts the reactor core through corresponding stand pipe, all is provided with actuating mechanism on every control rod, the drywell outside is provided with heat rising baffle, the reactor core outside is provided with a core enclosure, reactor core enclosure upper portion links to each other with heat rising baffle lower part, heat rising baffle vertically upwards develops around the drywell, and the heat rising baffle top is located the coolant liquid level below, keeps apart the passageway and the decline passageway of coolant, the flash evaporation takes place in the passageway, be provided with a plurality of internal baffle in the passageway, evenly divide the passageway into a plurality of evenly to divide into with the heat transfer subassembly into each heat transfer subsystem, evenly divide the heat transfer subsystem into each branch passageway and evenly.

Still further, the vortex subassembly includes a plurality of spoiler and spoiler, the spoiler sets up in the passageway that rises, evenly divides the passageway that rises into a plurality of runners, the spoiler sets up on the inner wall of spoiler and heat rising baffle.

Still further, the sub heat exchange system comprises a plurality of adjustable heat exchangers, a grading bus pipeline and a grading relay pipeline, wherein two ends of the grading relay pipeline are respectively connected with different adjustable heat exchangers, one end of the grading bus pipeline is connected with the grading relay pipeline, and the other end of the grading bus pipeline is connected with a bus.

Still further, be provided with the hierarchical access valve on the hierarchical bus way, the hierarchical bus way is provided with hierarchical power valve with the top of hierarchical trunk line junction.

Further, a gas zone heat exchanger is arranged in the gas zone above the liquid level of the coolant.

Still further, the drywell top is provided with the drywell upper shrouding, the lower part of drywell is provided with the drywell shrouding, the drywell shrouding is located the reactor core and directly has a certain distance department.

Furthermore, the dry underground sealing plate is provided with a guide pipe, and the control rod is inserted into the reactor core through the corresponding guide pipe.

Further, the reactor core and the reactor core surrounding cylinder are placed on a supporting plate, the lower part of the supporting plate is fixedly connected with a supporting assembly, and the supporting assembly is connected with the bottom of the reactor vessel.

Further, the reactor vessel is connected to a concrete foundation.

Further, a safety valve is arranged at the top of the reactor vessel.

Compared with the prior art, the invention has the beneficial effects that: the invention aims to provide a nuclear heating reactor with a dry well and adjustable power, which reduces the pressure-bearing requirement on a reactor container by adopting normal pressure and improves the site selection convenience of a heating plant; the flow rate of the coolant in the reactor is improved by flash evaporation, and meanwhile, the flow channels are divided by the heat rising partition plates and the turbulent flow components so as to eliminate oscillation caused by flash evaporation and prolong the service life of the components in the reactor; and the passive air-cooled waste heat discharging safety system is adopted, so that the structure of the safety system is simplified, and the overall reliability and inherent safety of the reactor are improved. The invention provides a dry well design right above a reactor core for shortening the length of a control rod, optimizing a reactor core refueling process and better detecting conditions in a reactor vessel.

The reactor adopts full natural circulation, so that a main pump is omitted, the structure is simplified, and the inherent safety is improved. During normal operation, the coolant takes the reactor core as a heat source and the liquid zone heat exchanger as a heat trap to form cold-hot core level difference to drive natural circulation, the coolant is flashed in the ascending channel to improve driving force, and the turbulent flow component divides the flow channel in the ascending channel, so that oscillation caused by the flashing is eliminated, and damage to components caused by the oscillation is avoided.

The invention adopts the design that the reactor container is at normal pressure, compared with a pressurized water reactor, the pressure born by the pressure-bearing boundary of the primary loop of the reactor is reduced, the possibility of occurrence of cracking accidents and loss accidents of coolant is reduced, and the inherent safety is improved; meanwhile, the design of each system and pipeline can be simplified under normal pressure, and the site selection of a heating plant is more convenient.

The invention adopts the dry well design, greatly shortens the length of the control rod, is convenient for overhauling and maintaining the reactor, and can fix the measuring assembly, the instrument and the like in the reactor on the dry well wall.

The invention adopts the heat exchange system with adjustable power, and can adjust the valve according to actual requirements to obtain required output power.

The invention is provided with various safety measures such as a gas zone heat exchanger, a safety valve and the like, the gas zone heat exchanger can discharge heat carried by steam accumulated at the upper end socket in the reactor out of the reactor, and the pressure born by a reactor container is timely reduced; the safety valve is normally closed, and can be opened when the heat and pressure at the upper part in the reactor vessel exceed a certain value or the heat exchanger in the gas zone fails and cannot discharge heat, so that pressure is released in time to prevent more serious accidents.

Drawings

The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention. In the drawings:

FIG. 1 is a schematic diagram of a nuclear heating reactor with dry well power regulation according to the present invention;

FIG. 2 is a schematic view of a connection structure between a heat rising partition and an inner partition according to the present invention;

fig. 3 is a schematic structural diagram of a spoiler assembly according to the present invention.

1-reactor vessel, 2-reactor core, 3-dry well, 4-dry well upper seal plate, 5-dry well lower seal plate, 6-reactor core enclosure, 7-support plate, 8-support assembly, 9-control rod, 10-heat rising partition plate, 11-inner partition plate, 12-turbulence assembly, 12.1-turbulence plate, 12.2-turbulence plate, 13-gas zone heat exchanger, 14-safety valve, 15-bus, 16-sub heat exchange system, 16.1-adjustable heat exchanger, 16.2-staged bus channel, 16.3-staged relay line, 16.4-staged channel valve, 16.5-staged power valve, 17-concrete foundation.

Detailed Description

The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. It should be noted that, in the case of no conflict, embodiments of the present invention and features of the embodiments may be combined with each other, and the described embodiments are only some embodiments of the present invention, not all embodiments.

Referring to fig. 1-3, a nuclear heating reactor with dry wells for power adjustment is illustrated, which includes a reactor vessel 1, a core 2, a dry well 3, control rods 9, a thermal riser 10, a spoiler assembly 12, and an adjustable power heat exchange system, among other things.

The reactor core 2 and the dry well 3 are arranged inside the reactor vessel 1, the top end of the dry well 3 is connected with the upper portion of the reactor vessel 1, an upper dry well sealing plate 4 is arranged at the top of the dry well 3, the upper dry well sealing plate 4 is normally closed and can be opened according to requirements, a lower portion of the dry well 3 is provided with a lower dry well sealing plate 5, the dry well 3 extends from the top end of the reactor vessel 1 to the lower dry well sealing plate 5, and the lower dry well sealing plate 5 is located at a certain distance from the position right above the reactor core 2.

The inside of the dry well 3 is normal pressure and no coolant is provided, the number of the control rods 9 is multiple, the control rods 9 are arranged in the dry well 3, guide pipes are arranged on the underground dry well sealing plates 5, the control rods 9 are inserted into the reactor core 2 through the corresponding guide pipes, each control rod 9 is provided with a driving mechanism, and the control rods 9 are driven through the driving mechanisms.

The utility model discloses a reactor, including dry well 3, reactor vessel 1, support assembly 8, reactor vessel 1 and concrete foundation 17, reactor vessel 1 top is provided with relief valve 14, the dry well 3 outside is provided with heat rising baffle 10, the reactor vessel 2 outside is provided with reactor vessel 6, reactor vessel 6 upper portion links to each other with heat rising baffle 10 lower part, reactor vessel 2 and reactor vessel 6 are placed on backup pad 7, backup pad 7 below links to each other with support assembly 8 is fixed, support assembly 8 links to each other with reactor vessel 1 bottom, reactor vessel 1 links to each other with concrete foundation 17.

The heat rising partition board 10 vertically develops upwards around the dry well 3, the top end of the heat rising partition board 10 is positioned below the liquid level of the coolant, a rising channel and a falling channel of the coolant are isolated by the heat rising partition board 10, and the coolant flashes in the rising channel so as to realize natural circulation and strengthen driving force. Be provided with a plurality of internal baffle 11 in the passageway that rises, evenly cut apart into a plurality of reposition of redundant personnel passageway with the passageway that rises, all be provided with vortex subassembly 12 in every subchannel, it is hot vortex subassembly 12 includes a plurality of spoiler 12.1 and spoiler 12.2, the spoiler 12.1 sets up in the passageway that rises, evenly divides the passageway that rises into a plurality of runners, the spoiler 12.2 sets up on the inner wall of spoiler 12.1 and heat rising baffle 10.

Taking three stages as an example, the adjustable power heat exchange system comprises a bus 15 and a plurality of sub heat exchange systems 16, wherein the bus 15 is arranged in the dry well 3, each sub heat exchange system 16 is in a sub-channel, and the sub heat exchange systems 16 are connected with the bus 15. The sub heat exchange system 16 comprises a plurality of adjustable heat exchangers 16.1, a grading bus channel 16.2 and a grading relay pipeline 16.3, wherein two ends of the grading relay pipeline 16.3 are respectively connected with different adjustable heat exchangers 16.1, one end of the grading bus channel 16.2 is connected with the grading relay pipeline 16.3, the other end of the grading bus channel is connected with the bus 15, a grading channel valve 16.4 is arranged on the grading bus channel 16.2, and a grading power valve 16.5 is arranged above the joint of the grading bus channel 16.2 and the grading relay pipeline 16.3. The corresponding valve may be adjusted according to the power demand.

A gas zone heat exchanger 13 is arranged in the gas zone above the liquid level of the coolant, and the pressure and the flash evaporation degree of the gas zone can be controlled by adjusting the power of the gas zone heat exchanger 13 according to the requirement.

The embodiments of the invention disclosed above are intended only to help illustrate the invention. The examples are not intended to be exhaustive or to limit the invention to the precise forms disclosed. Many modifications and variations are possible in light of the above teaching. The embodiments were chosen and described in order to best explain the principles of the invention and the practical application, to thereby enable others skilled in the art to best understand and utilize the invention.

Claims (10)

1. A nuclear heating reactor with dry well adjustable power, characterized by: the device comprises a reactor container (1), a reactor core (2), a dry well (3), control rods (9), a heat rising partition plate (10), a turbulent flow assembly (12) and an adjustable power heat exchange system, wherein the reactor core (2) and the dry well (3) are arranged inside the reactor container (1), the dry well (3) is positioned right above the reactor core (2) at a certain distance, the top end of the dry well (3) is connected with the upper part of the reactor container (1), normal pressure and no coolant exist in the dry well (3), the control rods (9) are multiple, the control rods (9) are arranged in the dry well (3) and are inserted into the reactor core (2) through corresponding guide pipes, a driving mechanism is arranged on each control rod (9), the outside of the dry well (3) is provided with a heat rising partition board (10), the outside of the reactor core (2) is provided with a reactor core surrounding barrel (6), the upper part of the reactor core surrounding barrel (6) is connected with the lower part of the heat rising partition board (10), the heat rising partition board (10) vertically develops upwards around the dry well (3), the top end of the heat rising partition board (10) is positioned below the liquid level of the coolant, a rising channel and a falling channel of the coolant are isolated by the heat rising partition board (10), flash evaporation occurs in the rising channel, a plurality of inner partition boards (11) are arranged in the rising channel, the rising channel is evenly divided into a plurality of sub-channels, each sub-runner is internally provided with a turbulence assembly (12), the adjustable power heat exchange system comprises a bus (15) and a plurality of sub-heat exchange systems (16), the bus (15) is arranged in the dry well (3), each sub-runner is internally provided with a sub-heat exchange system (16), and the sub-heat exchange systems (16) are connected with the bus (15).

2. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the vortex subassembly (12) includes a plurality of spoiler (12.1) and spoiler (12.2), spoiler (12.1) set up in the passageway that rises, evenly divide into a plurality of runners with the passageway that rises, spoiler (12.2) set up on the inner wall of spoiler (12.1) and heat rising baffle (10).

3. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the sub heat exchange system (16) comprises a plurality of adjustable heat exchangers (16.1), a grading bus channel (16.2) and a grading relay pipeline (16.3), wherein two ends of the grading relay pipeline (16.3) are respectively connected with different adjustable heat exchangers (16.1), one end of the grading bus channel (16.2) is connected with the grading relay pipeline (16.3), and the other end of the grading bus channel is connected with the bus (15).

4. A nuclear heating reactor with adjustable power for dry wells as defined in claim 3, wherein: the hierarchical bus channel (16.2) is provided with a hierarchical channel valve (16.4), and a hierarchical power valve (16.5) is arranged above the connection part of the hierarchical bus channel (16.2) and the hierarchical relay pipeline (16.3).

5. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: a gas zone heat exchanger (13) is arranged in the gas zone above the liquid level of the coolant.

6. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the utility model discloses a reactor core, including dry well (3), reactor core (2), dry well (3) top is provided with dry well upper end shrouding (4), the lower part of dry well (3) is provided with dry well underground end shrouding (5), dry well underground end shrouding (5) are located certain distance department directly over reactor core (2).

7. A nuclear heating reactor with adjustable power for a drywell according to claim 6, wherein: the dry underground sealing plate (5) is provided with a guide pipe, and the control rod (9) is inserted into the reactor core (2) through the corresponding guide pipe.

8. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the reactor is characterized in that the reactor core (2) and the reactor core surrounding cylinder (6) are arranged on the supporting plate (7), the lower part of the supporting plate (7) is fixedly connected with the supporting assembly (8), and the supporting assembly (8) is connected with the bottom of the reactor container (1).

9. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the reactor vessel (1) is connected to a concrete foundation (17).

10. A nuclear heating reactor with adjustable power for dry wells as defined in claim 1, wherein: the top of the reactor vessel (1) is provided with a safety valve (14).