Reactor core
By using a modular core design and annular fuel structure, the problems of heat removal and stability in heat pipe cooled reactors have been solved, achieving high reliability and safety of the reactor, adapting to different model requirements, reducing manufacturing difficulty and improving neutron economy.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-12-17
- Publication Date
- 2026-03-17
AI Technical Summary
In heat pipe cooled reactors, the manufacturing and operational stability issues of numerous fuel elements and heat pipes can prevent heat from being effectively removed, thus affecting reactor safety.
The reactor core is modularized into multiple core modules, employing annular fuel and heat pipe structures. A lead layer and a helium layer are placed between the heat pipe and the annular fuel to reduce neutron leakage and thermal stress. Heat is transferred using the core matrix, and shutdown rods are installed for reactivity control.
It improves the reliability and safety of the reactor, enabling it to maintain normal operation even when multiple heat pipes fail, reducing manufacturing difficulty and improving neutron economy, and achieving long-term unmanned autonomous operation.
Smart Images
Figure CN121687569A_ABST
Abstract
Description
Technical Field
[0001] The embodiments of this application relate to the field of reactor core structures, and particularly to a reactor core. Background Technology
[0002] The statements herein are provided merely as background information in connection with this application and do not necessarily constitute prior art.
[0003] Heat pipe cooled reactors use heat pipes instead of coolant to remove the heat generated by the reactor. The reactor core needs to be equipped with a large number of fuel elements and heat pipes, which brings great difficulties to the reactor manufacturing process. At the same time, the numerous heat pipes may be damaged or fail due to manufacturing defects or transient effects during operation, which may prevent the heat released by the fuel elements near the heat pipes from being effectively removed, potentially affecting the safe operation of the reactor. Summary of the Invention
[0004] A brief overview of this application is provided below to offer a basic understanding of certain aspects thereof. It should be understood that this overview is not an exhaustive summary of the application. It is not intended to identify key or essential parts of the application, nor is it intended to limit its scope. Its purpose is merely to present certain concepts in a simplified form as a prelude to the more detailed description that follows.
[0005] This application provides a reactor core, which includes: a plurality of reactor core modules, a first support body, a second support body, and a stop rod. The plurality of reactor core modules are supported by the first support body and the second support body and are disposed between the first support body and the second support body. The stop rod is disposed within the first support body. The reactor core modules are configured in a modular form.
[0006] The reactor core provided in the embodiments of this application, by setting the reactor core modules in a modular form, allows the reactor core modules to be pre-manufactured, which can adapt to the needs of different models and reduce the difficulty of reactor core processing and manufacturing; by setting multiple reactor core modules between the first support body and the second support body, multiple reactor core modules can be supported and fixed, making the internal structure of the reactor core compact.
[0007] Another aspect of this application provides a reactor core, which includes a plurality of annular fuels, a plurality of heat pipes, and a core substrate. The plurality of annular fuels are configured to be embedded in the core substrate, and the plurality of heat pipes are configured to be embedded in the corresponding plurality of annular fuels.
[0008] The reactor core provided in the embodiments of this application, by setting heat pipes embedded in the corresponding annular fuel and setting the annular fuel embedded in the reactor core matrix, allows the heat generated by the annular fuel to be transferred through the reactor core matrix to the heat pipes set in other annular fuels when the heat pipes fail, and timely dissipation of heat. This enables the reactor to continue to operate normally when more than 3 adjacent heat pipes fail, further improving the reliability of the reactor and facilitating long-term unmanned autonomous operation. Attached Figure Description
[0009] To further illustrate the above and other advantages and features of this application, the specific embodiments of this application will be described in more detail below with reference to the accompanying drawings. The drawings, together with the following detailed description, are included in and form a part of this specification. Elements having the same function and structure are indicated by the same reference numerals. It should be understood that these drawings only depict typical examples of this application and should not be considered as limiting the scope of this application.
[0010] Figure 1 This is a schematic diagram of the core structure provided in an embodiment of this application; Figure 2 This is a schematic diagram of the core module provided in an embodiment of this application; Figure 3 This is a partial structural diagram of the core module provided in an embodiment of this application.
[0011] Explanation of reference numerals in the attached figures: 1. Core module; 11. Annular fuel; 12. Heat pipe; 13. Lead layer; 14. Helium layer; 2. First support; 3. Second support; 4. Stop rod; 5. Core matrix; 100. Core. Detailed Implementation
[0012] Exemplary embodiments of this application will be described below with reference to the accompanying drawings. For clarity and brevity, not all features of actual implementations are described in the specification. However, it should be understood that many implementation-specific decisions must be made in the development of any such actual embodiment to achieve the developer's specific goals, such as complying with constraints related to the system and business, and these constraints may vary depending on the implementation. Furthermore, it should be understood that while development work can be very complex and time-consuming, such development work is merely a routine task for those skilled in the art who benefit from the content of this application.
[0013] It should also be noted that, in order to avoid obscuring this application with unnecessary details, only the equipment structure and / or processing steps closely related to the solution according to this application are shown in the accompanying drawings, while other details that are not closely related to this application are omitted.
[0014] The following disclosure provides several different implementations or examples for carrying out this application. To simplify the disclosure of this application, specific examples of components and methods are described below. Of course, these are merely examples and are not intended to limit this application. In the description of the embodiments of this application, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.
[0015] Existing research indicates that when more than three adjacent heat pipes fail near fuel elements, the core matrix temperature and stress will exceed limits, causing the reactor to malfunction or even threatening reactor safety.
[0016] To address the aforementioned problems, embodiments of this application provide, on the one hand, a reactor core; Figure 1 This is a schematic diagram of the core structure provided in an embodiment of this application, as shown below. Figure 1 As shown, it includes: multiple core modules 1, a first support body 2, a second support body 3, and a stop rod 4. The multiple core modules 1 are supported by the first support body 2 and the second support body 3 and are disposed between the first support body 2 and the second support body 3. The stop rod 4 is disposed inside the first support body 2. The core modules 1 are configured in a modular form.
[0017] The reactor core 100 provided in the embodiments of this application, by setting the reactor core module 1 in the form of a module, allows the reactor core module 1 to be pre-manufactured, which can adapt to the needs of different models and reduce the processing and manufacturing difficulty of the reactor core 100; by setting multiple reactor core modules 1 between the first support body 2 and the second support body 3, multiple reactor core modules 1 can be supported and fixed, making the internal structure of the reactor core 100 compact.
[0018] Figure 2 This is a schematic diagram of the core module structure provided in an embodiment of this application. In some embodiments, such as... Figure 2 As shown, the core module 1 includes annular fuel 11 and multiple heat pipes 12. The multiple heat pipes 12 are embedded in the annular fuel 11 and are configured to conduct heat generated by the annular fuel 11.
[0019] Multiple heat pipes 12 are embedded within the annular fuel 11, allowing the annular fuel 11 to directly transfer heat to the heat pipes 12. This minimizes the heat transfer path and reduces thermal resistance. Furthermore, the large contact area between the annular fuel 11 and the heat pipes 12 enhances the overall heat transfer capacity and efficiency of the heat pipes. This enables a more compact reactor core for the same power output, achieving miniaturization; or, with the same core volume, higher output power can be obtained.
[0020] Since the fuel element is set as an annular fuel 11, its structure is axisymmetric, resulting in a more uniform distribution of thermal stress, which reduces the risk of fatigue and failure. At the same time, the annular fuel 11 and the heat pipe 12 each form an independent barrier, so the fission gas will not directly diffuse or leak into the vacuum cavity of the heat pipe 12, further preventing the failure of the heat pipe 12.
[0021] In some embodiments, the core 100 further includes a core substrate 5, a plurality of annular fuels 11 are configured to be embedded in the core substrate 5, a plurality of heat pipes 12 are configured to be embedded in the annular fuels 11, and the heat pipes 12 and the annular fuels 11 are configured to reduce neutron leakage.
[0022] By embedding multiple annular fuels 11 into the core substrate 5, the heat generated by the annular fuels 11 can be transferred from their outer surface to the core substrate 5. Combined with the heat pipes 12 installed inside the annular fuels 11 to conduct heat to their inner surface, the temperature difference between the inner and outer surfaces of the annular fuels 11 is smaller, and the center temperature is lower, thereby reducing the maximum operating temperature of the fuel and improving the safety margin.
[0023] The following problems exist in the process of modularizing the reactor core: neutrons and gamma rays can leak through the heat pipe 12 channel inside the annular fuel 11, requiring the heat pipe 12 to withstand a high radiation dose. Furthermore, excessive neutron leakage necessitates more fuel to achieve criticality. By configuring the space between the heat pipe 12 and the annular fuel 11 to reduce neutron leakage, the fuel mass required for reactor criticality can be reduced, and a gamma shielding effect can be achieved, thereby improving the reactor's neutron economy.
[0024] Figure 3 This is a partial structural diagram of the core module provided in an embodiment of this application. In some embodiments, such as... Figure 3 As shown, a lead layer 13 can be provided between the heat pipe 12 and the annular fuel 11. The lead layer 13 is liquid at the reactor operating temperature to absorb the stress generated by the thermal expansion of the heat pipe 12 and the annular fuel 11, and to prevent the connection between the annular fuel 11 and the heat pipe 12 and the core substrate 5 from cracking due to the different thermal expansion coefficients of the materials at high temperatures. The above method can solve the problem of cracking due to the different thermal expansion coefficients of the materials in the modular core.
[0025] In the process of modularizing the reactor core, there is also the problem of thermal stress caused by the difference in thermal expansion coefficients between the core matrix and the annular fuel due to heating.
[0026] To address the aforementioned issues, in some embodiments, the core substrate 5 and the annular fuel 11 are positioned to reduce the thermal stress between them, preventing them from being squeezed together due to uneven expansion, thus preventing core structure deformation or damage and ensuring core integrity.
[0027] In some embodiments, a helium layer 14 may be provided between the core substrate 5 and the annular fuel 11 to reduce the thermal stress between the core substrate 5 and the annular fuel 11, thereby preventing deformation or damage to the core 100 structure.
[0028] In some embodiments, the stop rod 4 is disposed within the first support 2, which can better integrate reactivity control components and save core space.
[0029] In some embodiments, such as Figure 1 As shown, the first support body 2 can be set near the center of the core 100. The shutdown rod 4 is set in the first support body 2, which can effectively affect the neutron flux distribution, realize efficient reactivity control and shutdown; avoid the core 100 center power peak is too high, make the core power distribution more uniform, thereby reducing the maximum fuel temperature and improving safety.
[0030] In some embodiments, the stop rod 4 can be configured to include a circular stop rod and an annular stop rod, which form a sleeve structure. Since the annular stop rod is positioned between the circular stop rod and the core module 1, it has a larger neutron flux gradient and is more sensitive to power changes, enabling it to absorb a large number of neutrons from the periphery and rapidly reduce reactor power. The circular stop rod is located near the center of the core 100, and its insertion introduces extremely strong negative reactivity, ensuring that the reactor reaches and maintains a deep subcritical state.
[0031] In some embodiments, the circular stop bar can be configured to have a greater stop depth than the annular stop bar, ensuring that safe shutdown can be achieved by inserting the circular stop bar alone when the annular stop bar cannot be fully inserted due to a malfunction.
[0032] By coordinating the insertion depths of the circular stop rods and the annular stop rods, the power distribution inside the reactor core 100 can be precisely adjusted without changing the total power, thereby optimizing the temperature field of the heat pipe 12 and the annular fuel 11 and improving system efficiency and safety.
[0033] In another aspect, this application provides a reactor core 100, which includes a plurality of annular fuels 11, a plurality of heat pipes 12, and a reactor core substrate 5. The plurality of annular fuels 11 are configured to be embedded in the reactor core substrate 5, and the plurality of heat pipes 12 are configured to be embedded in the corresponding plurality of annular fuels 11.
[0034] The reactor core 100 provided in the embodiments of this application, by setting the heat pipes 12 to be embedded in the corresponding annular fuel 11 and setting the annular fuel 11 to be embedded in the reactor core matrix 5, allows the heat generated by the annular fuel 11 to be transferred through the reactor core matrix 5 to the heat pipes 12 set in other annular fuels 11 when the heat pipes 12 are damaged or fail, and also allows for the timely dissipation of heat. This enables the reactor to continue to operate normally when more than 3 adjacent heat pipes 12 fail, further improving the reliability of the reactor and facilitating long-term unmanned autonomous operation.
[0035] In some embodiments, the heat pipe 12 and the annular fuel 11 are configured to reduce neutron leakage. Since neutrons and gamma rays can leak through the channels of the heat pipe 12 inside the annular fuel 11, the heat pipe 12 needs to withstand a high radiation dose. At the same time, excessive neutron leakage requires more fuel to achieve criticality. By configuring the heat pipe 12 and the annular fuel 11 to reduce neutron leakage, the fuel mass required for reactor criticality can be reduced, and a gamma shielding effect can be achieved, thereby improving the reactor's neutron economy.
[0036] In some embodiments, a lead layer 13 may be provided between the heat pipe 12 and the annular fuel 11. The lead layer 13 is liquid at the reactor operating temperature to absorb the stress generated by the thermal expansion of the heat pipe 12 and the annular fuel 11, and to prevent the connection between the annular fuel 11 and the heat pipe 12 and the core substrate 5 from cracking at high temperatures due to the different thermal expansion coefficients of the materials.
[0037] In some embodiments, a helium layer 14 may be provided between the core substrate 5 and the annular fuel 11 to reduce the thermal stress between the core substrate 5 and the annular fuel 11, thereby preventing deformation or damage to the core 100 structure.
[0038] Regarding the embodiments of this application, it should also be noted that, without conflict, the embodiments of this application and the features in the embodiments can be combined with each other to obtain new embodiments.
[0039] The above are merely specific embodiments of this application, but the scope of protection of this application is not limited thereto. The scope of protection of this application shall be determined by the scope of the claims.
Claims
1. A core, characterized in that It comprises: a plurality of core modules, a first support body, a second support body, and a shutdown rod, the plurality of core modules are arranged to be supported by the first support body and the second support body, and are arranged between the first support body and the second support body, the shutdown rod is arranged in the first support body, wherein the core modules are arranged in a module form.
2. The core according to claim 1, wherein the core modules comprise annular fuels and a plurality of heat pipes, the plurality of heat pipes are embedded in the annular fuels and arranged to conduct heat generated by the annular fuels.
3. The core according to claim 2, wherein the core further comprises a core base, a plurality of the annular fuels are arranged to be embedded in the core base, a plurality of heat pipes are arranged to be embedded in the annular fuels, a space is arranged between the heat pipes and the annular fuels to reduce neutron leakage.
4. The core according to claim 3, wherein a lead layer is arranged between the heat pipes and the annular fuels, the lead layer being liquid at a temperature at which the reactor operates.
5. The core according to claim 3, wherein a space is arranged between the core base and the annular fuels to reduce thermal stress between the core base and the annular fuels.
6. The core according to claim 5, wherein a helium layer is arranged between the core base and the annular fuels.
7. A core, comprising: a plurality of annular fuels, a plurality of heat pipes, and a core base, the plurality of annular fuels are arranged to be embedded in the core base, and the plurality of heat pipes are arranged to be embedded in a corresponding plurality of the annular fuels.
8. The core according to claim 7, wherein a space is arranged between the heat pipes and the annular fuels to reduce neutron leakage.
9. The core according to claim 8, wherein a lead layer is arranged between the heat pipes and the annular fuels, the lead layer being liquid at a temperature at which the reactor operates.
10. The core according to claim 8, wherein a helium layer is arranged between the core base and the annular fuels to reduce thermal stress between the core base and the annular fuels.