Modularized pool type lead-based fast neutron high-flux experimental research reactor
By using a modular pool design, the reactor core and main equipment are separated into independent modules. Lead-based coolant is used to circulate and remove heat, which solves the problems of insufficient safety and economy of existing fast neutron research reactors and meets the scientific research needs of high-flux nuclear reactions and irradiation tests.
Patent Information
- Application Number
- CN202511645365.4
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-11-11
- Publication Date
- 2026-02-06
AI Technical Summary
Existing fast neutron high-flux research reactors are mainly water-cooled thermal neutron reactors. The scarcity of fast neutron irradiation resources severely restricts the development of advanced nuclear energy systems. Furthermore, existing designs are complex, lack safety and economic efficiency, and are difficult to meet the irradiation testing requirements of advanced nuclear fuels and materials.
The modular pool design places the reactor core in an independent reactor module, while the main circulating pump and main heat exchanger are placed in an independent heat exchange unit module. Heat is removed by circulating lead-based coolant, which reduces the radial dimensions and weight of the reactor vessel, improves safety and reliability, and increases the space for experimental operation.
It has achieved fast neutron high-flux nuclear reactions, meeting the accelerated irradiation testing requirements of nuclear fuels and materials, improving the reactor's operational flexibility and equipment maintainability, simplifying design and installation, and reducing irradiation dose.
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Figure CN121483673A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of nuclear reactor technology, specifically to a modular pool-type lead-based fast neutron high-flux experimental research reactor. Background Technology
[0002] "Fast neutron high flux" refers to a special nuclear environment that can generate an extremely dense high-energy neutron field (where the proportion of neutrons with energies higher than 0.1 MeV is greater than 70%). High-flux experimental research reactors are large-scale, comprehensive nuclear facilities that provide high-quality neutron sources and realistic service environments for various types of reactors. They meet the requirements for long-term irradiation testing and performance evaluation of advanced nuclear fuels and materials, verification of key technologies for advanced nuclear reactors, and cutting-edge basic research in fields such as neutron science, materials science, energy science, and biological science. They are essential major scientific and technological infrastructure for the development of advanced nuclear energy technologies. Currently, the research reactors built globally are mainly water-cooled thermal neutron reactors, with only one sodium-cooled fast neutron high flux research reactor in Russia in operation. Fast neutron irradiation resources are extremely scarce, severely restricting the innovative development of fourth-generation advanced nuclear energy systems based on the fast neutron energy spectrum and next-generation advanced nuclear power technologies.
[0003] Against this backdrop, in order to support the rapid development of advanced nuclear energy and nuclear power technologies, primarily fast neutron reactors, there is an urgent need to build a new generation of metal-cooled fast neutron high-flux research reactors. For example, a certain type of sodium-cooled fast neutron high-flux research reactor currently under construction has a thermal power of 150 MW and a maximum core neutron flux rate of 5.3 × 10⁻⁶. 15 n / cm 2 The -s reactor has a maximum core irradiance of 35 dpa / year and adopts a pressure vessel-type three-loop design, where the primary loop coolant is high-temperature liquid metallic sodium, the intermediate loop coolant is sodium, and the tertiary loop uses high-temperature steam. A soon-to-be-built sodium-cooled fast neutron high-flux research reactor will have a thermal power of 300 MW and a maximum core irradiance of 30 dpa / year, employing a pool-type three-loop design. An accelerator-driven lead-based cold fast neutron high-flux research reactor, with a thermal power of 100 MW and a maximum irradiance exceeding 20 dpa / year, adopts an integral vessel-type two-loop design.
[0004] Among them, lead-based fast neutron high-flux research reactors typically employ a simpler two-loop design, operate at lower temperatures, and their lead-based coolants do not undergo violent chemical reactions with air or water, exhibiting significant inherent safety advantages. This makes lead-based reactors an important development direction for metal-cooled fast neutron high-flux research reactors. Therefore, it is essential to explore safer, more economical, more efficient, and more flexible lead-based fast neutron high-flux research reactors to strongly support subsequent engineering construction. Summary of the Invention
[0005] This invention provides a modular pool-type lead-based fast neutron high-flux experimental research reactor, which can meet the scientific research needs of accelerated irradiation testing and performance testing of nuclear fuels and materials, verification of key technologies of advanced nuclear reactors, and basic research in cutting-edge fields. It also features simple layout, flexible and safe operation, convenient maintenance, and sufficient experimental operation space.
[0006] This invention is achieved through the following technical solution:
[0007] This invention provides a modular pool-type lead-based fast neutron high-flux experimental research reactor, comprising: a reactor pit structure with a reaction working chamber, the reaction working chamber being a gas containment chamber; a reactor module, installed in the middle of the reaction working chamber, capable of performing controlled nuclear reactions and cooling the reactor based on a lead-based coolant (liquid lead or lead-bismuth eutectic alloy); and multiple heat exchange unit modules, installed within the reaction working chamber, evenly spaced around the reactor module circumferentially and spaced apart from the reactor module, connected to the corresponding pipelines of the reactor module via coolant outflow and inflow pipes, capable of driving the lead-based coolant to circulate between the reactor module and the heat exchange unit modules to remove the heat generated in the reactor core.
[0008] The modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention includes a closed dry crater structure, a reactor module, and a heat exchange unit module. The reactor module is capable of controlled nuclear reactions and is cooled by a lead-based coolant. Specifically, the core of the lead-based fast neutron high-flux reactor is arranged within an independent reactor module. Simultaneously, the heat exchange unit module is connected to the corresponding port of the reactor module via coolant outflow and inflow pipes, enabling the lead-based coolant to circulate between the reactor module and the heat exchange unit module, carrying away the heat generated by the reactor. In other words, the primary loop system, including the main circulation pump and main heat exchanger, is integrated. By arranging key equipment in independent heat exchange unit modules, the radial dimensions and dry (wet) weight of the reactor vessel can be significantly reduced, as well as the technical difficulty of design, manufacturing, and installation, thereby improving economy, safety, and reliability. It can also greatly increase the experimental operation space and refueling operation space at the top of the reactor, which is very beneficial for setting up large-scale experimental devices at the top of the reactor, improving the reactor's operational flexibility. Furthermore, it can reduce the technical difficulty of heating and heat preservation of the reactor vessel and heat exchange vessel, and significantly reduce the radiation dose of the main equipment in the primary loop system, such as the main circulating pump and main heat exchanger, thereby improving the maintainability of the main equipment in the primary loop.
[0009] Among them, the reactor module conducts a controlled nuclear reaction, and the heat exchange unit module drives the lead-based coolant to cool the reactor module, which can realize a fast neutron high-flux nuclear reaction, and then carry out accelerated irradiation testing and performance testing of nuclear fuels and structural materials, thus meeting the scientific research needs of accelerated irradiation testing and performance testing of advanced nuclear fuels and materials.
[0010] Meanwhile, the reactor module and heat exchange unit module are installed in a closed dry reactor pit structure, and the working chamber of the nuclear reactor system in the reactor pit structure is a gas-containing chamber. That is, the reactor module and several heat exchange unit modules are arranged in the dry reactor pit, and there is no other filling material except gas. This is very beneficial for the installation, commissioning and maintenance of the nuclear reactor and the primary loop system, as well as the installation, commissioning and application and experimental operation of the radial test device outside the reactor vessel. In particular, the layout of the external neutron detector is more flexible, simpler and more efficient.
[0011] Combining key primary system equipment such as the main circulation pump and main heat exchanger into several independent heat exchange unit modules can significantly improve the efficiency of installation, commissioning, and maintenance of key equipment such as the main circulation pump and main heat exchanger. The number of key equipment such as the main circulation pump and main heat exchanger can be flexibly adjusted.
[0012] Therefore, the modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention can meet the scientific research needs of accelerated irradiation testing and performance testing of nuclear fuels and materials, verification of key technologies of advanced nuclear reactors, and basic research in cutting-edge fields. It also features simple layout, flexible and safe operation, convenient maintenance, and sufficient experimental operation space.
[0013] In an optional embodiment of this application, the reactor module includes: a reactor vessel, which is a hollow cavity structure; an in-core component installed at the bottom of the reactor vessel cavity; a reactor core located in the middle of the reactor vessel cavity and above the in-core component; and a control rod drive mechanism installed at the top of the reactor vessel, capable of controlling the depth to which the control rods are inserted into the reactor core to ensure that the reactor module can perform a controlled nuclear reaction.
[0014] In an optional embodiment of this application, the reactor core is installed inside the reactor vessel via a basket to facilitate the installation and replacement of the reactor core.
[0015] In an optional embodiment of this application, the reactor module further includes an irradiation test component for loading irradiated test specimens; the irradiation test component is vertically arranged, with its upper end extending to the outside of the top of the reactor vessel and its lower end extending into the reactor core, to ensure that the reactor module can undergo accelerated irradiation testing and performance testing of nuclear fuel and materials.
[0016] In an optional embodiment of this application, the reactor module further includes a refueling valve covering the top of the reactor vessel. The control rod drive mechanism and the upper end of the irradiation test component both extend through the refueling valve to facilitate the replacement of the reactor core and the irradiation test specimen.
[0017] In an optional embodiment of this application, the heat exchange unit module includes: a main heat exchanger, the medium inlet of the hot flow channel being connected to the coolant outlet pipe, and the cold flow channel of the main heat exchanger being connected to the secondary cooling system; and a main circulation pump, the medium inlet being connected to the medium outlet of the hot flow channel of the main heat exchanger, and the medium outlet being connected to the coolant inflow pipe, to ensure that the heat exchange unit module can drive the lead-based coolant to circulate between the reactor module and the heat exchange unit module and remove the heat generated by the reactor core.
[0018] In an optional embodiment of this application, the heat exchange unit module further includes a heat exchange container, in which the main heat exchanger and the main circulation pump are both installed. The heat exchange container accommodates the main circulation pump and the main heat exchanger, thereby reducing radiation and heat loss.
[0019] In an optional embodiment of this application, the heat exchange unit module further includes a heat insulation filling structure that fills the internal cavity of the heat exchange container to provide heat insulation for the main heat exchanger and the main circulating pump, thereby further reducing heat loss.
[0020] In an optional embodiment of this application, the heat-insulating filling structure is provided with: an inlet cavity connected in series between the coolant outlet pipe and the medium inlet of the hot runner of the main heat exchanger; a return cavity connected in series between the coolant inlet pipe and the medium outlet of the hot runner of the main heat exchanger; and a connecting cavity connected in series between the main heat exchanger and the main circulating pump, so as to connect the main circulating pump and the main heat exchanger, and connect the reactor module and the heat exchange unit module through the internal cavity of the heat-insulating filling structure, thereby replacing the direct connection pipes between the equipment, resulting in lower flow resistance, and the arrangement of key equipment such as the main circulating pump and the main heat exchanger can be flexibly adjusted according to the test requirements.
[0021] In an optional embodiment of this application, the main heat exchanger and the main circulating pump are arranged vertically side by side, and the connecting cavity is located at the lower end of the main heat exchanger and the main circulating pump, so as to facilitate the arrangement of the main heat exchanger and the main circulating pump and the setting of the connecting cavity.
[0022] In an optional embodiment of this application, a crater top cover is also included, which covers the upper end of the crater structure; the upper ends of the reactor module and the heat exchange unit module are both connected to the crater top cover, so as to seal and protect the crater through the crater top cover, while sharing the weight of the reactor module and the heat exchange unit module, and limiting the reactor module and the heat exchange unit module axially and radially.
[0023] In an optional embodiment of this application, the reactor module further includes a reactor support located at the bottom of the reactor module to facilitate adjustment of the height of the reactor module and ensure a reliable connection between the reactor module and the crater top cover.
[0024] In an optional embodiment of this application, the heat exchange unit module further includes a heat exchange support located at the bottom of the heat exchange unit module to facilitate adjustment of the height of the heat exchange unit module and ensure that the heat exchange unit module can be reliably connected to the top cover of the sump.
[0025] Compared with the prior art, the present invention has the following advantages and beneficial effects:
[0026] 1. The modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention includes a crater structure, a reactor module, and a heat exchange unit module. The core of the lead-based block neutron high-flux experimental research reactor is arranged in an independent reactor module. At the same time, key equipment of the primary loop system, such as the main circulating pump and the main heat exchanger, is arranged in an independent heat exchange unit module. This can significantly reduce the radial dimension and dry weight of the reactor vessel, as well as the technical difficulty of design, manufacturing, and installation, and improve economy, safety, and reliability. It can also greatly increase the experimental operation space and refueling operation space at the top of the reactor, which is very beneficial to the installation and commissioning of large-scale experimental devices, improves the operational flexibility of the reactor, and simplifies the heating and insulation technology of the reactor vessel and heat exchange vessel. It can also significantly reduce the radiation dose of the main equipment of the primary loop system, such as the main circulating pump and the main heat exchanger, thereby improving the maintainability of the main equipment of the primary loop system.
[0027] 2. The modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention conducts a controllable nuclear reaction through reactor modules, and the reactor core is cooled by lead-based cooling medium driven by heat exchange unit modules. This enables fast neutron high-flux nuclear reactions, thereby conducting accelerated irradiation tests and performance tests on nuclear fuels and materials, meeting the scientific research needs for accelerated irradiation tests and performance tests of advanced nuclear fuels and materials.
[0028] 3. The modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention arranges the reactor module and heat exchange unit module in a dry reactor pit, and there are no other filling materials except gas. This is very beneficial for the installation, commissioning and maintenance of the reactor primary loop system, as well as the installation, commissioning and application of the external radial test device of the reactor vessel. In particular, the layout of the external neutron detector is more flexible, simpler and more efficient.
[0029] 4. The modular pool-type lead-based fast neutron high-flux experimental research reactor provided by this invention can combine key equipment such as the main circulation pump and the main heat exchanger into several independent heat exchange unit modules, which can greatly improve the efficiency of installation, commissioning and maintenance of key equipment such as the main circulation pump and the main heat exchanger. The number of key equipment such as the main circulation pump and the main heat exchanger can be flexibly adjusted. Attached Figure Description
[0030] To more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings used in the embodiments will be briefly described below. It should be understood that the following drawings only show some embodiments of the present invention and should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can be obtained based on these drawings without creative effort.
[0031] In the attached diagram:
[0032] Figure 1 A schematic diagram of the axial arrangement of the primary loop system of the modular pool-type lead-based fast neutron high-flux experimental research reactor provided in this embodiment of the invention;
[0033] Figure 2 A schematic diagram of the radial arrangement of the primary loop system modules of the four heat exchange units of the modular pool-type lead-based fast neutron high flux experimental research reactor provided in an embodiment of the present invention;
[0034] Figure 3 A schematic diagram of the radial arrangement of the primary loop system module of the three heat exchange units of the modular pool-type lead-based fast neutron high flux experimental research reactor provided in an embodiment of the present invention;
[0035] Figure 4 This is a schematic diagram of the radial arrangement of the primary loop system modules of the three heat exchange units of the modular pool-type lead-based fast neutron high flux experimental research reactor provided in an embodiment of the present invention.
[0036] The attached figures include reference numerals and their corresponding component names:
[0037] 1-Reactor module, 2-Heat exchange unit module, 3-Coolant outflow pipe, 4-Coolant inflow pipe, 5-Pit structure, 6-Core, 7-Basket, 8-Reactor vessel, 9-In-core components, 10-Control rod drive mechanism, 11-Refueling valve, 12-Irradiation test component, 13-Main circulation pump, 14-Main heat exchanger, 15-Heat exchange vessel, 16-Reactor support, 17-Heat exchange support, 18-Inlet cavity, 19-Return cavity, 20-Connecting cavity, 21-Insulated filling structure, 22-Pit top cover, 23-Secondary loop connection pipe. Detailed Implementation
[0038] To make the objectives, technical solutions, and advantages of the embodiments of this application clearer, the technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. The components of the embodiments of this application described and shown in the accompanying drawings can generally be arranged and designed in various different configurations.
[0039] Therefore, the following detailed description of the embodiments of this application provided in the accompanying drawings is not intended to limit the scope of the claimed application, but merely to illustrate selected embodiments of the application. All other embodiments obtained by those skilled in the art based on the embodiments of this application without inventive effort are within the scope of protection of this application.
[0040] It should be noted that similar reference numerals and letters in the following figures denote similar items; therefore, once an item is defined in one figure, it does not need to be further defined and explained in subsequent figures. Unless otherwise specified, the embodiments and features described in these embodiments can be combined with each other.
[0041] In the description of the embodiments of this application, the indicated orientation or positional relationship is based on the orientation or positional relationship shown in the accompanying drawings, or the orientation or positional relationship that the product of this application is usually placed in when in use, or the orientation or positional relationship that is commonly understood by those skilled in the art. It is only for the convenience of describing this application and simplifying the description, and is not intended to indicate or imply that the device or component referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, it should not be construed as a limitation of this application.
[0042] In the description of this application, unless otherwise expressly specified and limited, the terms "set up," "install," "connect," and "link" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a direct connection or an indirect connection through an intermediate medium; and they can refer to the internal connection of two components. Those skilled in the art can understand the specific meaning of the above terms in this application based on the specific circumstances.
[0043] Example
[0044] Combination Figure 1 and Figure 2 This embodiment provides a modular pool-type lead-based fast neutron high-flux experimental research reactor, comprising: a reactor pit structure 5, which is provided with a reaction working chamber, the reaction working chamber being a gas containment chamber; a reactor module 1, installed in the middle of the reaction working chamber, capable of performing controlled nuclear reactions and cooled based on a lead-based coolant (liquid lead or lead-bismuth eutectic alloy); and multiple heat exchange unit modules 2, installed within the reaction working chamber, evenly spaced around the circumference of the reactor module 1 and spaced apart from the reactor module 1, connected to the corresponding pipelines of the reactor module 1 through coolant outflow pipes 3 and coolant inflow pipes 4, capable of driving the lead-based coolant to circulate between the reactor module 1 and the heat exchange unit modules 2 and carrying away the heat generated in the reactor core.
[0045] Specifically, in this embodiment, the reactor core 6 is separated from the main equipment of the primary loop system, forming independent functional modules. The reactor core 6 is arranged in an independent reactor vessel 8, constituting reactor module 1. Key equipment of the primary loop system, such as the main circulating pump and the main heat exchanger 14, is arranged in several independent heat exchange vessels, constituting heat exchange unit modules 2. Reactor module 1 and heat exchange unit modules 2 are connected by short pipes. That is, in this embodiment, the primary loop coolant system of the pool-type lead-based fast neutron high flux experimental research reactor consists of one reactor module 1 and several heat exchange unit modules 2, with the several heat exchange unit modules 2 (usually 2 to 4 groups) symmetrically arranged around the reactor module 1.
[0046] Combination Figure 2 In one optional implementation, the primary coolant system of the research reactor is divided into one reactor module 1 and four heat exchange unit modules 2, with adjacent heat exchange unit modules 2 arranged symmetrically around the reactor module 1 at 90-degree intervals within the dry reactor pit structure 5.
[0047] Combination Figure 3 In one optional implementation, the primary coolant system of the research reactor is divided into one reactor module 1 and three heat exchange unit modules 2, with adjacent heat exchange unit modules 2 spaced at 120-degree intervals and evenly arranged around the reactor module 1 within the dry reactor pit structure 5.
[0048] Combination Figure 4 In one optional implementation, the primary coolant system of the research reactor is divided into one reactor module 1 and two heat exchange unit modules 2, with adjacent heat exchange unit modules 2 arranged symmetrically around the reactor module 1 at 180-degree intervals within the dry reactor pit structure 5.
[0049] Continue to combine Figure 1The reactor module 1 includes: a reactor vessel 8, which is a hollow cavity structure; an internal component 9, installed at the bottom of the cavity of the reactor vessel 8; a core 6, located in the middle of the cavity of the reactor vessel 8; and a control rod drive mechanism 10, installed at the top of the reactor vessel 8, which can control the depth of the control rods inserted into the core 6 to ensure that the reactor module 1 can carry out a controlled nuclear reaction.
[0050] It is known that the reactor vessel 8 is typically cylindrical in shape. Generally, the reactor core 6 is installed inside the reactor vessel 8 via a basket 7 to facilitate the installation and replacement of the reactor core 6. In other words, the reactor module 1 is located at the center of the reactor pit, and the reactor vessel 8 is cylindrical in shape, consisting of the following components from the inside out: reactor core 6, basket 7, and reactor vessel 8.
[0051] In this embodiment, the reactor module 1 further includes an irradiation test component 12, which is used to load irradiation test specimens. The irradiation test component 12 is arranged vertically, with its upper end extending to the outside of the top of the reactor vessel 8 and its lower end extending into the reactor core 6, to ensure that the reactor module 1 can undergo accelerated irradiation testing and performance testing of nuclear fuel and materials.
[0052] Generally, the reactor module 1 also includes a refueling valve 11, which covers the top of the reactor vessel 8. The upper ends of the control rod drive mechanism 10 and the irradiation test component 12 both extend through the refueling valve 11 to facilitate the replacement of the reactor core 6 and the irradiation test specimen.
[0053] Specifically, the heat exchange unit module 2 includes: a main heat exchanger 14, the medium inlet of the hot flow channel is connected to the coolant outlet pipe 3, and the cold flow channel of the main heat exchanger 14 is connected to the secondary cooling system; and a main circulation pump 13, the medium inlet of which is connected to the medium outlet of the hot flow channel of the main heat exchanger 14, and the medium outlet of which is connected to the coolant inflow pipe 4, so as to ensure that the heat exchange unit module 2 can drive the lead-based coolant to circulate between the reactor module 1 and the heat exchange unit module 2 and remove the heat generated by the reactor core.
[0054] In this embodiment, the heat exchange unit module 2 further includes a heat exchange container 15. The heat exchanger 14 and the main circulation pump 13 are both installed in the heat exchange container 15 so that the main circulation pump 13 and the main heat exchanger 14 can be accommodated in the heat exchange container 15, which can reduce radiation and reduce heat loss.
[0055] To facilitate the arrangement of equipment such as the main circulating pump 13 and the main heat exchanger 14, the heat exchange container 15 in the heat exchange unit module 2 is rectangular in shape.
[0056] The heat exchange unit module 2 further includes a heat insulation filling structure 21, which fills the internal cavity of the heat exchange container 15 to provide heat insulation for the main heat exchanger 14 and the main circulating pump 13, thereby further reducing heat loss.
[0057] Furthermore, the heat-insulating filling structure 21 is provided with: an inlet cavity 18, connected in series between the coolant outlet pipe 3 and the medium inlet of the hot flow channel of the main heat exchanger 14; a return cavity 19, connected in series between the coolant inlet pipe 4 and the medium outlet of the hot flow channel of the main heat exchanger 14; and a connecting cavity 20, connected in series between the main heat exchanger 14 and the main circulating pump 13, so as to connect the main circulating pump 13 and the main heat exchanger 14, and connect the reactor module 1 and the heat exchange unit module 2 through the internal cavity of the heat-insulating filling structure 21, thereby replacing the direct connection pipes between the equipment, resulting in lower flow resistance, and the arrangement of key equipment such as the main circulating pump 13 and the main heat exchanger 14 can be flexibly adjusted according to the test requirements.
[0058] The main heat exchanger 14 and the main circulation pump 13 are arranged vertically side by side, and the connecting cavity 20 is located at the lower end of the main heat exchanger 14 and the main circulation pump 13, so as to facilitate the arrangement of the main heat exchanger 14 and the main circulation pump 13 and the setting of the connecting cavity 20.
[0059] In other words, a lead-based coolant flow channel is pre-set in the heat exchange container 15, without setting up a dedicated connecting pipe. The lead-based coolant enters the reserved space (feed chamber) at the top of the main heat exchanger 14 from the reactor module 1 through the coolant outflow pipe 3, flows through the main heat exchanger 14 into the connecting channel (connecting cavity 20) between the main circulation pump 13 and the bottom of the main heat exchanger 14, then flows through the main circulation pump 13, and then enters the reserved space at the top of the main circulation pump 13 (return cavity 19), and then re-enters the reactor module 1 through the coolant inflow pipe 4. The secondary loop coolant carries away the heat generated by the reactor through the main heat exchanger 14 and the secondary loop connecting pipe 23.
[0060] Typically, each heat exchange unit module 2 contains one heat exchange container 15, one main circulation pump 13, and two main heat exchangers 14, with the main circulation pump 13 positioned in the middle of the two main heat exchangers 14.
[0061] It should be noted that within the same heat exchange unit module 2, if two or more main circulation pumps 13 are installed, the upper reserved space between the main circulation pumps 13 is interconnected, and the height of the free liquid level of the lead-based coolant is the same; if two or more main heat exchangers 14 are installed, the upper reserved space between the main heat exchangers 14 is interconnected, and the height of the free liquid level of the lead-based coolant is the same.
[0062] Furthermore, this embodiment also includes a crater top cover 22, which covers the upper end of the crater structure 5; the upper ends of the reactor module 1 and the heat exchange unit module 2 are both connected to the crater top cover 22, so as to seal and protect the crater through the crater top cover 22, while sharing the weight of the reactor module 1 and the heat exchange unit module 2, and limiting the reactor module 1 and the heat exchange unit module 2 axially and radially.
[0063] The reactor module 1 also includes a reactor support 16, which is located at the bottom of the reactor module 1 to facilitate the adjustment of the height of the reactor module 1 and ensure that the reactor module 1 can be reliably connected to the crater top cover 22.
[0064] Correspondingly, the heat exchange unit module 2 also includes a heat exchange support 17, which is located at the bottom of the heat exchange unit module 2 to facilitate the adjustment of the height of the heat exchange unit module 2 and ensure that the heat exchange unit module 2 can be reliably connected to the top cover 22 of the sump.
[0065] In summary, the pool-type lead-based fast neutron high-flux experimental research reactor provided in this embodiment includes a crater structure 5, a reactor module 1, and a heat exchange unit module 2. The core 6 of the lead-based block neutron high-flux reactor is arranged within a separate reactor module 1, while key primary circuit equipment such as the main circulating pump 13 and the main heat exchanger 14 are arranged in the opposing heat exchange unit module 2. This significantly reduces the radial dimensions and dry (wet) weight of the reactor vessel 8, as well as the technical difficulty of design, manufacturing, and installation, improving economy, safety, and reliability. It also greatly increases the experimental and refueling operation space at the top of the reactor, which is highly beneficial for the installation of large experimental devices, improving the reactor's operational flexibility. Furthermore, it simplifies the heating and insulation techniques for the reactor vessel 8 and the heat exchange vessel 15, and significantly reduces the radiation dose of the primary circuit main equipment such as the main circulating pump 13 and the main heat exchanger 14, thereby improving the maintainability of the primary circuit main equipment.
[0066] The reactor module 1 enables a controlled nuclear reaction, and the heat exchange unit module 2 drives the lead-based cooling medium to cool the reactor core, which can achieve a fast neutron high-flux nuclear reaction. This allows for accelerated irradiation testing and performance evaluation of nuclear fuels and materials, meeting the research needs for accelerated irradiation testing and performance evaluation of advanced nuclear fuels and materials.
[0067] Furthermore, reactor module 1 and heat exchange unit module 2 are installed inside the reactor pit structure 5, and the reaction working chamber of the reactor pit structure 5 is a gas containment chamber. That is, reactor module 1 and heat exchange unit module 2 are arranged in a dry reactor pit, and there are no other filling materials except gas. This is very beneficial for the installation, commissioning and maintenance of the reactor primary coolant system, as well as the installation, commissioning and application of the external radial test device of the reactor vessel 8. In particular, the layout of the external neutron detector is more flexible, simpler and more efficient.
[0068] In addition, combining key equipment such as the main circulation pump 13 and the main heat exchanger 14 into several independent heat exchange unit modules 2 can greatly improve the efficiency of installation, commissioning and maintenance of key equipment such as the main circulation pump 13 and the main heat exchanger 14. The number of key equipment such as the main circulation pump 13 and the main heat exchanger 14 can be flexibly adjusted.
[0069] In summary, the pool-type lead-based fast neutron high-flux experimental research reactor provided in this embodiment can meet the scientific research needs for accelerated irradiation testing and performance evaluation of nuclear fuels and materials. It also features simple layout, flexible and reliable operation, convenient maintenance, and ample experimental space. This significantly enhances the design performance of the lead-based fast neutron high-flux research reactor in terms of safety, economy, efficiency, and flexibility, greatly improving its engineering feasibility.
[0070] The specific embodiments described above further illustrate the purpose, technical solution, and beneficial effects of the present invention. It should be understood that the above description is only a specific embodiment of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.
Claims
1. A modular pool type lead based fast neutron high flux test research reactor characterized in that, The application relates to a nuclear reactor, which comprises: a reactor pit structure (5) provided with a reaction working cavity which is a gas containing cavity; a reactor module (1) installed in the middle of the reaction working cavity, capable of carrying out controllable nuclear reaction and cooled by lead-based coolant; a plurality of heat exchange unit modules (2) installed in the reaction working cavity, uniformly and spacedly arranged around the periphery of the reactor module (1) and spacedly arranged with the reactor module (1), connected with the corresponding pipelines of the reactor module (1) through coolant outflow pipelines (3) and coolant inflow pipelines (4), capable of driving the lead-based coolant to circulate between the reactor module (1) and the heat exchange unit module (2) and take away the heat generated by the reactor core.
2. The modular pool type lead based fast neutron high flux test research reactor of claim 1, wherein, The reactor module (1) comprises: a reactor vessel (8) which is a hollow cavity structure; a reactor internal component (9) installed at the bottom of the inner cavity of the reactor vessel (8); a reactor core (6) located in the middle of the inner cavity of the reactor vessel (8); a control rod drive mechanism (10) installed at the top of the reactor vessel (8) and capable of controlling the depth of the control rod inserted into the reactor core (6).
3. The modular pool type lead based fast neutron high flux test research reactor of claim 2, wherein, The reactor core (6) is installed in the inner cavity of the reactor vessel (8) through a hanging basket (7).
4. The modular pool type lead based fast neutron high flux test research reactor of claim 2, wherein, The reactor module (1) further comprises an irradiation test component (12) for loading irradiation test pieces; The irradiation test component (12) is vertically arranged, the upper end of the irradiation test component (12) extends out of the top of the reactor vessel (8), and the lower end extends into the reactor core (6).
5. The modular pool type lead based fast neutron high flux test research reactor of claim 4, wherein, The reactor module (1) further comprises a fuel replacement cock (11) which is arranged on the top of the reactor vessel (8), the control rod drive mechanism (10) and the upper end of the irradiation test component (12) both pass through the fuel replacement cock (11).
6. The modular pool type lead based fast neutron high flux test research reactor of claim 1, wherein, The heat exchange unit module (2) comprises: a main heat exchanger (14) with a medium inlet of a hot runner connected with the coolant outflow pipeline (3), and a cold runner of the main heat exchanger (14) connected with a two-loop cooling system; a main circulating pump (13) with a medium inlet connected with a medium outlet of the hot runner of the main heat exchanger (14), and a medium outlet connected with the coolant inflow pipeline (4).
7. The modular pool type lead based fast neutron high flux test research reactor of claim 6, wherein, The heat exchange unit module (2) further comprises a main heat exchange vessel (15), and the main heat exchanger (14) and the main circulating pump (13) are both installed in the main heat exchange vessel (15).
8. The modular pool type lead based fast neutron high flux test research reactor according to claim 7, characterized in that, The heat exchange unit module (2) further comprises a heat insulation filling structure (21) which fills the internal cavity of the main heat exchange vessel (15).
9. The modular pool type lead based fast neutron high flux test research reactor of claim 8, wherein, The heat insulation filling structure (21) is provided with: an inflow cavity (18) connected in series between the coolant outflow pipeline (3) and the medium inlet of the hot runner of the heat exchanger (14); an outflow cavity (19) connected in series between the coolant inflow pipeline (4) and the medium outlet of the hot runner of the heat exchanger (14); a communication cavity (20) connected in series between the main heat exchanger (14) and the main circulating pump (13).
10. The modular pool type lead based fast neutron high flux test research reactor of claim 9, wherein, The main heat exchanger (14) is vertically arranged in parallel with the main circulating pump (13), and the communication cavity (20) is located at the lower end of the main heat exchanger (14) and the main circulating pump (13).
11. The modular pool type lead based fast neutron high flux test research reactor according to any one of claims 1 to 10, characterized in that, A top cover (22) of the pit is further included, which covers the upper end of the pit structure (5). The upper end of the reactor module (1) and the heat exchange unit module (2) are connected with the top cover (22) of the pit.
12. The modular pool type lead based fast neutron high flux test research reactor of claim 11, wherein, The reactor module (1) further includes a reactor support (16) located at the bottom of the reactor module (1).
13. The modular pool type lead based fast neutron high flux test research reactor of claim 12, wherein, The heat exchange unit module (2) further includes a heat exchange support (17) located at the bottom of the heat exchange unit module (2).