A regulated power nuclear heat supply reactor with dry well

Abstract

The application provides an adjustable power nuclear heat supply reactor with a dry well, and belongs to the technical field of nuclear reactors. The application solves the problem of limited power of the existing nuclear heat supply reactor. The adjustable power nuclear heat supply reactor comprises a reactor container, a reactor core, a dry well, control rods, a thermal rise baffle, a turbulence assembly and an adjustable power heat exchange system. The reactor core and the dry well are arranged in the reactor container. The dry well is under normal pressure and has no coolant. The control rods are arranged in the dry well and inserted into the reactor core. The dry well is provided with the thermal rise baffle. The thermal rise baffle separates the rising channel and the falling channel of the coolant. The coolant is flashed in the rising channel. The turbulence assembly is arranged in each shunt. 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. Each shunt is provided with a sub heat exchange system. The sub heat exchange system is connected with the bus. The adjustable power nuclear heat supply reactor is mainly used for nuclear heat supply reactors.

Description

Technical Field

[0001] This invention belongs to the field of nuclear reactor technology, and in particular relates to a nuclear heating reactor with adjustable power and a dry well. Background Technology

[0002] In recent decades, there have been many designs for heating reactors both domestically and internationally, such as the Soviet Union's shell-type integrated natural circulation pressurized water reactor ATS-500, the Canadian SLOW POKE natural circulation pool-type heating reactor, and Sweden's Atgesta. However, their economic efficiency and safety have not been widely recognized, and they have problems such as complex structures.

[0003] Most existing heating reactors employ natural circulation designs. However, the driving force and heat-carrying capacity of natural circulation are limited. When the core power is high, single-phase natural circulation alone is insufficient to remove the heat generated in the core. Therefore, methods such as reducing reactor power or increasing the height difference between the hot and cold sections within the reactor are often used to improve the reactor's natural circulation capability. These methods, on the one hand, limit the reactor power level and restrict the reactor's application requirements; on the other hand, they increase the reactor's structural size, which is detrimental to reactor miniaturization.

[0004] When the coolant in the reactor approaches saturation temperature, flashing can occur due to pressure reduction. Flashing can effectively enhance the driving force of natural circulation and increase the flow rate of the primary coolant loop, but it can also cause large-scale oscillations, which is detrimental to the operation of a nuclear heating reactor.

[0005] The control rods of a reactor are typically inserted into the pressure vessel head. When the overall length of the reactor is long, the length of the control rods must also increase. A significant portion of the control rods are immersed in coolant and subjected to heat and radiation, increasing the risk of bending or even breakage. Summary of the Invention

[0006] In view of this, the present invention aims to propose a nuclear heating reactor with adjustable power and a dry well to solve the problem of limited power in existing nuclear heating reactors.

[0007] To achieve the above objectives, the present invention adopts the following technical solution: a nuclear heating reactor with adjustable power and a dry well, comprising a reactor vessel, a core, a dry well, control rods, a heat rise baffle, a turbulence assembly, and an adjustable power heat exchange system. The core and the dry well are disposed inside the reactor vessel. The dry well is located at a certain distance directly above the core, and its top is connected to the upper part of the reactor vessel. The dry well is at atmospheric pressure and contains no coolant. Multiple control rods are disposed within the dry well and inserted into the core through corresponding guide tubes. Each control rod is equipped with a drive mechanism. A heat rise baffle is disposed on the outside of the dry well. A core conduit is provided on the outside of the reactor core. The upper part of the core conduit is connected to the lower part of the heat riser baffle. The heat riser baffle extends vertically upward around the dry well, and the top of the heat riser baffle is located below the coolant liquid level. The heat riser baffle separates the rising channel and the falling channel of the coolant. The coolant flashes in the rising channel. Several inner baffles are provided in the rising channel, which are evenly divided into several sub-channels. Each sub-channel is provided with a turbulence component. The adjustable power heat exchange system includes a main bus and several sub-heat exchange systems. The main bus is located in the dry well, and each sub-channel has a sub-heat exchange system connected to the main bus.

[0008] Furthermore, the turbulence assembly includes several turbulence plates and turbulence diffusers. The turbulence plates are disposed within the rising channel, dividing the rising channel into multiple flow channels evenly. The turbulence diffusers are disposed on the inner walls of the turbulence plates and the heat rise baffle.

[0009] Furthermore, the sub-heat exchange system includes several adjustable heat exchangers, a tiered bus connection, and a tiered relay pipeline. The two ends of the tiered relay pipeline are respectively connected to different adjustable heat exchangers. One end of the tiered bus connection is connected to the tiered relay pipeline, and the other end is connected to the bus.

[0010] Furthermore, a tiered connection valve is provided on the tiered bus connection channel, and a tiered power valve is provided above the connection point between the tiered bus connection channel and the tiered relay pipeline.

[0011] Furthermore, a gas zone heat exchanger is provided in the gas zone above the coolant liquid surface.

[0012] Furthermore, the top of the dry well is provided with a dry well upper sealing plate, and the bottom of the dry well is provided with a dry well lower sealing plate, which is located at a certain distance directly above the reactor core.

[0013] Furthermore, a guide tube is provided on the dry well bottom sealing plate, and the control rod is inserted into the core through the corresponding guide tube.

[0014] Furthermore, the reactor core and the core shroud are placed on a support plate, the support plate is fixedly connected to a support assembly below, and the support assembly is connected to the bottom of the reactor vessel.

[0015] Furthermore, the reactor vessel is connected to a concrete foundation.

[0016] Furthermore, a safety valve is installed on top of the reactor vessel.

[0017] Compared with existing technologies, the beneficial effects of this invention are as follows: The purpose of this invention is to provide a nuclear heating reactor with adjustable power and a dry well. It utilizes atmospheric pressure to reduce the pressure requirements on the reactor vessel and improves the site selection convenience of the heating plant. It increases the coolant flow rate within the reactor by using flash evaporation, while simultaneously eliminating oscillations caused by flash evaporation by setting up heat rise baffles and turbulence-disrupting components to divide the flow channels, thus extending the service life of in-core components. Furthermore, it employs a passive gas-cooled residual heat removal safety system, simplifying the safety system structure and improving the overall reliability and inherent safety of the reactor. To shorten the control rod length, optimize the core refueling process, and better monitor the conditions inside the reactor vessel, this invention proposes a dry well design directly above the core.

[0018] The reactor described in this invention employs a fully natural circulation system, eliminating the need for a main pump, simplifying the structure, and improving inherent safety. During normal operation, the coolant uses the reactor core as a heat source and the liquid zone heat exchanger as a heat sink to create a temperature difference between the hot and cold cores, driving natural circulation. Flash evaporation of the coolant occurs within the rising channel, thereby increasing the driving force. Meanwhile, the turbulence-disrupting components divide the flow channels within the rising channel, eliminating oscillations caused by flash evaporation and preventing component damage caused by oscillations.

[0019] This invention adopts a design where the reactor vessel is under atmospheric pressure, which reduces the pressure on the primary circuit pressure boundary of the reactor compared to a pressurized water reactor, thereby reducing the possibility of rupture accidents and coolant leakage accidents and improving inherent safety. At the same time, atmospheric pressure can simplify the design of various systems and pipelines and make the site selection of heating plants more convenient.

[0020] This invention employs a dry well design, which significantly shortens the length of the control rods. The dry well also facilitates the inspection and maintenance of the reactor, and the reactor's measuring components and instruments can be fixed on the dry well wall.

[0021] This invention employs an adjustable power heat exchange system, which allows valves to be adjusted according to actual needs to obtain the required output power.

[0022] This invention incorporates various safety measures, such as a gas zone heat exchanger and a safety valve. The gas zone heat exchanger can discharge the heat carried by the steam accumulated at the upper head of the reactor into the reactor, thereby reducing the pressure on the reactor vessel in a timely manner. The safety valve is normally closed, but can be opened when the heat and pressure in the upper part of the reactor vessel exceed a certain value, or when the gas zone heat exchanger fails and cannot discharge the heat, so as to release pressure in a timely manner and prevent more serious accidents from occurring. Attached Figure Description

[0023] The accompanying drawings, which form part of this invention, are used to provide a further understanding of the invention. The illustrative embodiments of the invention and their descriptions are used to explain the invention and do not constitute an undue limitation of the invention. In the drawings:

[0024] Figure 1 This is a schematic diagram of a nuclear heating reactor structure with adjustable power and a dry well, as described in this invention.

[0025] Figure 2 This is a schematic diagram of the connection structure between the heat-raising partition and the inner partition according to the present invention;

[0026] Figure 3 This is a schematic diagram of the arrangement of the turbulence components described in this invention.

[0027] 1-Reactor vessel, 2-Core, 3-Dry well, 4-Dry well top cover plate, 5-Dry well bottom cover plate, 6-Core enclosure, 7-Support plate, 8-Support assembly, 9-Control rod, 10-Heat riser baffle, 11-Inner baffle, 12-Breakout assembly, 12.1-Breakout plate, 12.2-Breakout generator, 13-Gas zone heat exchanger, 14-Safety valve, 15-Bus, 16-Sub-heat exchange system, 16.1-Adjustable heat exchanger, 16.2-Stage bus connection, 16.3-Stage relay pipeline, 16.4-Stage connection valve, 16.5-Stage power valve, 17-Concrete foundation. Detailed Implementation

[0028] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. It should be noted that, unless otherwise specified, the embodiments and features in the embodiments of the present invention can be combined with each other, and the described embodiments are only some embodiments of the present invention, not all embodiments.

[0029] See Figure 1-3 This embodiment describes an adjustable-power nuclear heating reactor with a dry well, which includes a reactor vessel 1, a reactor core 2, a dry well 3, control rods 9, a heat rise baffle 10, a turbulence assembly 12, and an adjustable-power heat exchange system, etc.

[0030] The reactor core 2 and dry well 3 are located inside the reactor vessel 1. The top of the dry well 3 is connected to the upper part of the reactor vessel 1. The top of the dry well 3 is provided with a dry well upper sealing plate 4, which is normally closed but can be opened as needed. The bottom of the dry well 3 is provided with a dry well lower sealing plate 5. The dry well 3 extends from the top of the reactor vessel 1 to the dry well lower sealing plate 5. The dry well lower sealing plate 5 is located at a certain distance directly above the reactor core 2.

[0031] The dry well 3 is under normal pressure and contains no coolant. There are multiple control rods 9, which are installed inside the dry well 3. A guide tube is installed on the bottom sealing plate 5 of the dry well. The control rods 9 are inserted into the core 2 through the corresponding guide tubes. Each control rod 9 is equipped with a drive mechanism, which drives the control rod 9.

[0032] A heat riser baffle 10 is provided on the outside of the dry well 3, and a core confinement tube 6 is provided on the outside of the core 2. The upper part of the core confinement tube 6 is connected to the lower part of the heat riser baffle 10. The core 2 and the core confinement tube 6 are placed on a support plate 7. The lower part of the support plate 7 is fixedly connected to a support assembly 8. The support assembly 8 is connected to the bottom of the reactor vessel 1. The reactor vessel 1 is connected to a concrete foundation 17. A safety valve 14 is provided on the top of the reactor vessel 1.

[0033] The heat-rising baffle 10 extends vertically upwards around the dry well 3, with its top end positioned below the coolant surface. The heat-rising baffle 10 separates the coolant's ascending and descending channels, allowing the coolant to flash-evaporate within the ascending channel to achieve natural circulation and enhance driving force. Several inner baffles 11 are installed within the ascending channel, evenly dividing it into several flow channels. Each flow channel is equipped with a flow-dispersing component 12, which includes several flow-dispersing plates 12.1 and flow-dispersing devices 12.2. The flow-dispersing plates 12.1 are positioned within the ascending channel, evenly dividing it into multiple flow channels, while the flow-dispersing devices 12.2 are positioned on the inner walls of the flow-dispersing plates 12.1 and the heat-rising baffle 10.

[0034] Taking a three-stage system as an example, the adjustable power heat exchange system includes a main bus 15 and several sub-heat exchange systems 16. The main bus 15 is located in the dry well 3, and each branch channel contains one sub-heat exchange system 16, which is connected to the main bus 15. Each sub-heat exchange system 16 includes several adjustable heat exchangers 16.1, a staged main bus connection 16.2, and a staged relay pipeline 16.3. Both ends of the staged relay pipeline 16.3 are connected to different adjustable heat exchangers 16.1. One end of the staged main bus connection 16.2 is connected to the staged relay pipeline 16.3, and the other end is connected to the main bus 15. A staged connection valve 16.4 is installed on the staged main bus connection 16.2, and a staged power valve 16.5 is installed above the connection point between the staged main bus connection 16.2 and the staged relay pipeline 16.3. The corresponding valves can be adjusted according to power requirements.

[0035] A gas zone heat exchanger 13 is provided in the gas zone above the coolant liquid surface. The power of the gas zone heat exchanger 13 can be adjusted as needed to control the pressure and flash evaporation degree of the gas zone.

[0036] The embodiments of the present invention disclosed above are merely illustrative of the invention. These embodiments do not exhaustively describe all details, nor do they limit the invention to the specific implementations described. Many modifications and variations can be made based on the content of this specification. This specification selects and specifically describes these embodiments to better explain the principles and practical applications of the invention, thereby enabling those skilled in the art to better understand and utilize the invention.

Claims

1. A nuclear heating reactor with adjustable power and a dry well, characterized in that: It includes a reactor vessel (1), a reactor core (2), a dry well (3), control rods (9), a heat riser (10), a turbulence assembly (12), and an adjustable power heat exchange system. The reactor core (2) and the dry well (3) are located inside the reactor vessel (1). The dry well (3) is located at a certain distance directly above the reactor core (2). The top of the dry well (3) is connected to the upper part of the reactor vessel (1). The dry well (3) is at atmospheric pressure and contains no coolant. There are multiple control rods (9). Multiple control rods (9) are installed inside the dry well (3) and inserted into the reactor core (2) through corresponding guide tubes. Each control rod (9) is equipped with a drive mechanism. A heat riser baffle (10) is installed outside the dry well (3), and a reactor core confinement cylinder (6) is installed outside the reactor core (2). The upper part of the reactor core confinement cylinder (6) is connected to the lower part of the heat riser baffle (10). The heat riser baffle (10) extends vertically upward around the dry well (3), and the top of the heat riser baffle (10) is located below the coolant liquid level. The rising and falling channels of the coolant are separated by a heat riser baffle (10). The coolant flashes in the rising channel. Several inner baffles (11) are provided in the rising channel to evenly divide the rising channel into several branch channels. Each branch channel is provided with a turbulence component (12). The adjustable power heat exchange system includes a main bus (15) and several sub-heat exchange systems (16). The main bus (15) is located in the dry well (3). Each branch channel has one sub-heat exchange system. 16), the sub-heat exchange system (16) is connected to the bus (15). The sub-heat exchange system (16) includes several adjustable heat exchangers (16.1), a graded bus connection (16.2) and a graded relay line (16.3). The two ends of the graded relay line (16.3) are respectively connected to different adjustable heat exchangers (16.1). One end of the graded bus connection (16.2) is connected to the graded relay line (16.3), and the other end is connected to the bus (15).

2. The adjustable-power nuclear heating reactor with a dry well according to claim 1, characterized in that: The turbulence assembly (12) includes several turbulence plates (12.1) and turbulence generators (12.2). The turbulence plates (12.1) are arranged in the rising channel and divide the rising channel into multiple flow channels evenly. The turbulence generators (12.2) are arranged on the inner walls of the turbulence plates (12.1) and the heat rise baffle (10).

3. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: A tiered connection valve (16.4) is provided on the tiered bus connection (16.2), and a tiered power valve (16.5) is provided above the connection between the tiered bus connection (16.2) and the tiered relay line (16.3).

4. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: A gas zone heat exchanger (13) is provided in the gas zone above the coolant liquid surface.

5. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: The top of the dry well (3) is provided with a dry well upper sealing plate (4), and the bottom of the dry well (3) is provided with a dry well lower sealing plate (5). The dry well lower sealing plate (5) is located at a certain distance directly above the core (2).

6. A nuclear heating reactor with adjustable power and a dry well according to claim 5, characterized in that: The dry well bottom sealing plate (5) is equipped with a guide pipe, and the control rod (9) is inserted into the core (2) through the corresponding guide pipe.

7. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: The reactor core (2) and the reactor core shroud (6) are placed on the support plate (7), and the support plate (7) is fixedly connected to the support assembly (8) below. The support assembly (8) is connected to the bottom of the reactor vessel (1).

8. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: The reactor vessel (1) is connected to the concrete foundation (17).

9. A nuclear heating reactor with adjustable power and a dry well according to claim 1, characterized in that: A safety valve (14) is installed on the top of the reactor vessel (1).

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