Irradiation test device, method of determining structure parameters of a device body of the irradiation test device, method of testing performance of nuclear fuel, and nuclear fuel

Abstract

Embodiments of the present application relate to the field of nuclear power technology, and in particular to an irradiation test device, a method for determining structural parameters of a device body of the irradiation test device, a method for testing nuclear fuel performance, and nuclear fuel. The device comprises: the device body is arranged in a channel of a reactor; a containing assembly is arranged to be put into or taken out of the device body and contains a plurality of nuclear fuel units; the device body and the containing assembly are arranged such that the device body is heated by a coolant in the channel, the heat is transferred to the containing assembly, and the containing assembly transfers the heat to the plurality of nuclear fuel units. The device of the embodiments of the present application can change the temperature of the nuclear fuel units without redesigning the irradiation test device under the condition that the power of the reactor remains unchanged, simplifies the operation of the nuclear fuel units in and out of the reactor, and can realize continuous and variable temperature irradiation tests on the same nuclear fuel units in the same irradiation test device, thereby improving the efficiency of testing the performance of the nuclear fuel.

Description

Technical Field

[0001] The embodiments of this application relate to the field of nuclear power technology, specifically to an irradiation test apparatus, a method for determining the structural parameters of the apparatus body, a method for testing the performance of nuclear fuel, and nuclear fuel. Background Technology

[0002] The statements herein are provided only as background information in connection with this application and do not necessarily constitute prior art.

[0003] Understanding the behavior of nuclear fuel under irradiation is essential in the development of new nuclear fuels. Currently, the performance of nuclear fuels is mainly tested through irradiation experiments. The performance of nuclear fuels is affected by many factors, such as temperature, burnup, and neutron flux. Current irradiation tests typically use full-size nuclear fuel pellets, but this testing method is not very efficient. 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] In a first aspect, embodiments of this application provide an irradiation test apparatus suitable for testing the performance of nuclear fuel within the pores of a reactor. The irradiation test apparatus includes: a device body disposed within the pores of the reactor; and a receiving assembly configured to accommodate or remove the device body from the device body, the receiving assembly being configured to accommodate multiple nuclear fuel units for performance testing. The device body and the receiving assembly are configured such that: the device body is heated by a coolant within the pores, which transfers heat to the receiving assembly, and the receiving assembly transfers heat to the multiple nuclear fuel units, and each nuclear fuel unit is heated to a different temperature.

[0006] The embodiments of this application, by setting the device body and the housing components to heat each nuclear fuel unit at different temperatures, can change the temperature of the nuclear fuel unit without redesigning the irradiation test device while keeping the reactor power constant. This simplifies the operation of loading and unloading nuclear fuel units from the reactor and enables continuous, variable-temperature irradiation tests on the same nuclear fuel unit in the same irradiation test device, thereby improving the efficiency of testing the performance of nuclear fuel.

[0007] Secondly, embodiments of this application also provide a method for determining the structural parameters of the device body of the irradiation testing apparatus of this application, wherein the structural parameters of the device body include its inner diameter and its outer diameter. The method includes the following steps: S10: determining a first heat transfer coefficient between the receiving component and the inner wall of the device body; S20: determining a second heat transfer coefficient between the outer wall of the device body and the coolant; S30: determining the temperature of the device body, the temperature of the outer surface of the receiving component, and the temperature of the coolant; S40: determining the thermal conductivity, specific heat capacity, and density of the device body; S50: determining the inner diameter and outer diameter of the device body based on the first heat transfer coefficient determined in step S10, the second heat transfer coefficient determined in step S20, the temperature of the device body, the temperature of the outer surface of the receiving component, and the temperature of the coolant determined in step S30, and the thermal conductivity, specific heat capacity, and density of the device body determined in step S40.

[0008] Thirdly, embodiments of this application also provide a method for testing the performance of nuclear fuel, comprising the following steps: S1: dividing the nuclear fuel into multiple nuclear fuel units; S2: placing the nuclear fuel units into the irradiation test apparatus of this application embodiment; S3: simultaneously conducting irradiation tests on multiple nuclear fuel units at different temperatures.

[0009] Fourthly, embodiments of this application also provide a nuclear fuel, which is prepared experimentally using the method for testing the performance of nuclear fuel according to embodiments of this application.

[0010] These and other advantages of this application will become more apparent from the following detailed description of preferred embodiments in conjunction with the accompanying drawings. Attached Figure Description

[0011] 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.

[0012] Figure 1 This is a schematic diagram of the structure of an irradiation testing apparatus according to an embodiment of this application;

[0013] Figure 2 yes Figure 1 The cross-sectional view of the irradiation test apparatus shown;

[0014] Figure 3 This is a schematic diagram of the structure of an irradiation testing apparatus according to another embodiment of this application;

[0015] Figure 4 This is a schematic diagram of the structure of an irradiation test apparatus according to yet another embodiment of this application;

[0016] Figure 5 This is a flowchart illustrating a method for determining the structural parameters of the device body of an irradiation testing apparatus according to an embodiment of this application;

[0017] Figure 6 This is a flowchart illustrating a method for testing the performance of nuclear fuel according to an embodiment of this application.

[0018] It should be noted that the accompanying drawings are not necessarily drawn to scale, but are shown only in a schematic manner without affecting the reader's understanding.

[0019] Explanation of reference numerals in the attached figures:

[0020] 10. Device body; 11. First body; 111. Inner wall; 112. Outer wall; 113. Space; 12. Second body; 121. First wall surface; 122. Second wall surface; 123. End;

[0021] 20. Retaining component; 21. Retaining element; 22. Thermal insulation element;

[0022] 30. Nuclear fuel unit;

[0023] 40. Coolant;

[0024] 50. Hole. Detailed Implementation

[0025] 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.

[0026] 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.

[0027] It should be noted that, unless otherwise defined, the technical or scientific terms used in this application shall have the ordinary meaning as understood by a person with ordinary skills in the field to which this application pertains.

[0028] In the description of the embodiments of this application, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0029] In related technologies, adjustable test parameters in accelerated irradiation tests include irradiation temperature, neutron flux, and irradiation time. For accelerated irradiation tests in these technologies, under constant reactor operating conditions, a single nuclear fuel element can typically only be set to one irradiation temperature. Changing the irradiation temperature requires redesigning the entire irradiation device and removing the nuclear fuel element from the existing device before placing it in a new one. This makes it impossible to conduct continuous irradiation tests at different time periods and temperatures, resulting in complex and inefficient testing operations.

[0030] To address the aforementioned technical problems, embodiments of this application provide an irradiation testing apparatus suitable for testing the performance of nuclear fuel within the pores of a reactor. Figure 1 This is a schematic diagram of the structure of an irradiation testing apparatus according to an embodiment of this application. Figure 2 yes Figure 1 The cross-sectional view of the irradiation test apparatus shown is as follows: Figure 1 and Figure 2 As shown, the irradiation test apparatus includes a device body 10 and a housing component 20.

[0031] The device body 10 is disposed within the duct 50 of the reactor.

[0032] The housing assembly 20 is configured to be inserted into or removed from the device body 10, and is configured to accommodate multiple nuclear fuel units 30 for testing their performance.

[0033] The device body 10 and the housing assembly 20 are configured such that the device body 10 is heated by a coolant 40 in the channel 50, which transfers heat to the housing assembly 20, and the housing assembly 20 transfers heat to a plurality of nuclear fuel units 30, and each nuclear fuel unit 30 is heated to a different temperature.

[0034] The embodiments of this application configure the device body 10 and the housing assembly 20 to heat each nuclear fuel unit 30 at different temperatures. This allows the temperature of the nuclear fuel unit 30 to be changed without redesigning the irradiation test apparatus while keeping the reactor power constant. This simplifies the operation of loading and unloading the nuclear fuel unit 30 from the reactor and enables continuous, variable-temperature irradiation tests on the same nuclear fuel unit 30 within the same irradiation test apparatus, thereby improving the efficiency of testing the performance of nuclear fuel.

[0035] In some embodiments, Figure 3This is a schematic diagram of the structure of an irradiation testing apparatus according to another embodiment of this application, as shown below. Figure 3 As shown, the device body 10 has an inner wall 111 and an outer wall 112, and is configured such that the inner wall 111 forms a space 113, the space 113 having the same length in the direction extending perpendicular to the inner wall 111; the receiving component 20 is configured to be able to be inserted into or removed from the space 113, the outer wall 112 is in contact with the coolant 40, and the distance of the outer wall 112 to the inner wall 111 is different in the direction extending along the inner wall 111, so that each nuclear fuel unit 30 is heated to a different temperature.

[0036] The embodiments of this application, by setting the space 113 formed by the inner wall 111 of the device body 10 to have the same length in the direction extending perpendicular to the inner wall 111, facilitate the uniformity of the size of the accommodating component 20 placed in the space 113. By setting the distance from the outer wall 112 of the device body 10 to the inner wall 111 to be different in the direction extending along the inner wall 111, it is possible to achieve different heating temperatures for the nuclear fuel unit 30 at different positions in the test space 113, which is beneficial to ensure the smooth conduct of the irradiation test.

[0037] It is understood that in the embodiments of this application, the inner wall 111 is the wall surface in the device body 10 that contacts the receiving component 20, and the outer wall 112 is the wall surface in the device body 10 that contacts the coolant 40.

[0038] In some embodiments, the shape of the device body 10 matches the shape of the reactor channel 50. For example... Figure 3 As shown, the device body 10 is a cylindrical component. In the extending direction of the inner wall 111 of the device body 10, the space 113 has the same length in the direction perpendicular to the inner wall 111. The distance from the outer wall 112 to the inner wall 111 is different in the direction extending along the inner wall 111. That is to say, the inner diameter of the device body 10 is constant, while the outer diameter of the device body 10 varies in segments.

[0039] In some embodiments, the ratio between the distance between the outer wall 112 at any position of the device body 10 and the corresponding inner wall 111 at any position and the minimum thickness of the device body 10 is greater than or equal to 1, and the number of segments of the outer diameter of the device body 10 is greater than or equal to 2.

[0040] In some embodiments, the shape and size of the receiving component 20 are configured to match the shape of the space 113. For example, if the space 113 is a cylindrical space 113, then the receiving component 20 may be configured to be cylindrical or disc-shaped.

[0041] In some embodiments, the distance from the outer wall 112 to the inner wall 111 is the same within the range extending along the space 113 of each nuclear fuel unit 30, so that different parts of each nuclear fuel unit 30 are heated to the same temperature, thereby ensuring the reliability of the irradiation results.

[0042] In some embodiments, such as Figures 1 to 3 As shown, the housing assembly 20 includes a housing 21, a heat insulation element 22, and a push-pull element (not shown in the figure). Multiple nuclear fuel units 30 are respectively disposed in different housings 21. The housings 21 are disposed in the device body 10. The heat insulation element 22 is disposed between two adjacent housings 21. The push-pull element is configured to be fixedly connected to the housings 21 so that the housings 21 can be placed into or removed from the device body 10.

[0043] The embodiments of this application configure the housing assembly 20 as including a housing member 21, a heat insulation member 22, and a push-pull member. The heat insulation member 22 can isolate the heat exchange between two adjacent housing assemblies 20 to ensure that the temperature of the nuclear fuel unit 30 in each housing assembly 20 meets the temperature value required for the irradiation test. By configuring the push-pull member to be fixedly connected to the housing member 21, it is easy to put the housing member 21 into the device body 10 or take it out of the device body 10. At the same time, by using the push-pull member to change the position of the housing member 21 in the device body 10, the temperature of the nuclear fuel unit 30 in the housing member 21 being heated can be adjusted.

[0044] In some embodiments, such as Figure 1 and Figure 2 As shown, the device body 10 includes a first body 11 and a second body 12. The first body 11 forms an inner wall 111 and an outer wall 112, and is configured to form a space 113 by the inner wall 111. The space 113 has the same length in the direction extending perpendicular to the inner wall 111. The receiving component 20 is disposed in the space 113. The outer wall 112 is in contact with the coolant 40, and the outer wall 112 is configured to have a different distance from the inner wall 111 extending to the inner wall 111, so that each nuclear fuel unit 30 is heated to a different temperature. The second body 12 is configured to match the shape of the first body 11, and the second body 12 can be disposed outside the first body 11 so that the distance between the two can be adjusted, thereby adjusting the contact area between the coolant 40 and the first body 11 and the second body 12.

[0045] The embodiments of this application, by configuring the device body 10 to include a first body 11 and a second body 12, and by placing the second body 12 outside the first body 11 and configuring the shapes of the second body 12 and the first body 11 to match, help to adjust the contact area between the coolant 40 and the first body 11 and the second body 12 by adjusting the distance between the first body 11 and the second body 12, thereby making the nuclear fuel unit 30 in the containment 21 at different positions in the space 113 heated to different temperatures, and thus have a wide range of applications.

[0046] like Figure 2 As shown, the space formed by the first wall surface 121 of the second body 12 can be used to accommodate part of the housing component 20. This space and the space 113 formed by the inner wall 111 of the first body 11 have the same length in the direction extending perpendicular to the inner wall 111. The second wall surface 122 of the second body 12 matches the outer wall 112 of the first body 11 and is in contact with the coolant 40. By changing the distance between the second wall surface 122 of the second body 12 and the outer wall 112 of the first body 11, or by changing the length of any segment wall surface in the direction extending from the inner wall 111, the contact area between the coolant 40 and the first body 11 and the second body 12 can be adjusted.

[0047] Understandable. Figure 3 The irradiation test apparatus shown is merely exemplary. The end 123 of the second body 12 may be in contact with or have a gap with the outer wall 112 of the first body 11. Figure 4 This is a schematic diagram of the structure of an irradiation testing apparatus according to another embodiment of this application, as shown below. Figure 4 As shown, there is a gap between the end 123 of the second body 12 and the outer wall 112 of the first body 11.

[0048] Embodiments of this application also provide a method for determining the structural parameters of the device body 10 of an irradiation testing apparatus, wherein the structural parameters of the device body 10 include its inner diameter and its outer diameter. Figure 5 This is a flowchart illustrating a method for determining the structural parameters of the device body of an irradiation testing apparatus according to an embodiment of this application, as shown below. Figure 5 As shown, the determination method includes the following steps S10 to S50.

[0049] S10: Determine the first heat transfer coefficient between the housing component 20 and the inner wall 111 of the device body 10.

[0050] S20: Determine the second heat transfer coefficient between the outer wall 112 of the device body 10 and the coolant 40.

[0051] S30: Determine the temperature of the device body 10, the temperature of the outer surface of the housing component 20, and the temperature of the coolant 40.

[0052] S40: Determine the thermal conductivity, specific heat capacity, and density of the device body 10.

[0053] S50: Based on the first heat transfer coefficient determined in step S10, the second heat transfer coefficient determined in step S20, the temperature of the device body 10 determined in step S30, the temperature of the outer surface of the housing component 20 and the temperature of the coolant 40, and the thermal conductivity, specific heat capacity and density of the device body 10 determined in step S40, determine the inner diameter and outer diameter of the device body 10.

[0054] The determination method provided in the embodiments of this application determines the inner diameter and outer diameter of the device body 10 based on the first heat transfer coefficient between the containment component 20 and the inner wall 111 of the device body 10, the second heat transfer coefficient between the outer wall 112 of the device body 10 and the coolant 40, the temperature of the device body 10, the temperature of the outer surface of the containment component 20, the temperature of the coolant 40, and the thermal conductivity, specific heat capacity, and density of the device body 10. This allows for the alteration of the thermal conductivity of the device body 10 by changing its inner and outer diameters, thereby adjusting the temperature at which the nuclear fuel unit 30 within the containment component 20 is heated. This allows for the alteration of the temperature of the nuclear fuel unit 30 without redesigning the irradiation test apparatus while maintaining the reactor power, simplifying the loading and unloading of the nuclear fuel unit 30. Furthermore, it enables continuous, specific variable-temperature irradiation tests on the same nuclear fuel unit 30 within the same irradiation test apparatus, thereby improving the efficiency of testing the performance of nuclear fuel.

[0055] In some embodiments, in step S50, the inner diameter and outer diameter of the device body 10 satisfy the following expressions (1) to (3):

[0056]

[0057] Where, ρ cd The density of the device body 10 is represented by cd; cd represents the density of the device body 10; c pcd T represents the isobaric specific heat capacity of the device body 10; cd The temperature of the device body 10 is represented by t; time is represented by r; distance is represented by λ. cd The thermal conductivity of the device body 10 is represented by r. ci ci represents the inner diameter of the device body 10; h represents the inner wall of the device body 10; u,cd Indicates the first heat transfer coefficient; u represents the housing component 20; T us The temperature of the outer surface of the housing component 20 is indicated; us indicates the outer wall of the housing component 20; r coThe outer diameter of the device body 10 is indicated by co; the outer wall of the device body 10 is indicated by h. f,cd Indicates the second heat transfer coefficient; f represents the coolant; T f This indicates the temperature of the coolant.

[0058] The method provided in the embodiments of this application, through the above expressions (1) to (3), is beneficial to improving the accuracy and reliability of the obtained inner diameter and outer diameter of the device body 10.

[0059] In some embodiments, the inner diameter of the device body 10 is the distance of the inner wall of the device body 10 in its radial direction, and the outer diameter of the device body 10 is the distance of the outer wall of the device body 10 in its radial direction.

[0060] It is understood that in the embodiments of this application, for any position of the device body 10 along its extension direction, the inner diameter and outer diameter of the device body 10 at that position are first determined, and then the distance from the outer wall to the inner wall of the device body 10 at that position can be determined.

[0061] Embodiments of this application also provide a method for testing the performance of nuclear fuel. Figure 6 This is a schematic flowchart of a method for testing the performance of nuclear fuel according to an embodiment of this application, as shown below. Figure 6 As shown, the test method includes the following steps S1 to S3.

[0062] S1: Divide the nuclear fuel into multiple nuclear fuel units 30.

[0063] S2: Place the nuclear fuel unit 30 into the irradiation test apparatus of this application embodiment.

[0064] S3: Simultaneously conduct irradiation tests on multiple nuclear fuel units 30 at different temperatures.

[0065] The testing method provided in the embodiments of this application, by placing multiple nuclear fuel units 30 obtained from the division into the irradiation test apparatus of the embodiments of this application, enables the irradiation test of multiple nuclear fuel units 30 at different temperatures in the same experimental apparatus, thereby improving the efficiency and convenience of the irradiation test.

[0066] In some embodiments, the testing method of this application further includes the following steps: S4: After steps S1-S3 are completed, the positions of multiple nuclear fuel units 30 in the irradiation test device are moved, and the irradiation test is performed again.

[0067] The testing method provided in the embodiments of this application allows for repeated irradiation tests without redesigning the irradiation device by moving the positions of multiple nuclear fuel units 30 within the irradiation test device, making the operation relatively simple.

[0068] In some embodiments, the testing method of this application further includes the following steps: S5: placing different nuclear fuel units 30 into the first body 11 and the second body 12 of the device body 10 respectively; S6: setting the first body 11 and the second body 12 in the reactor channel 50 with different matching methods so that the nuclear fuel units 30 can be subjected to irradiation tests at different temperatures.

[0069] The testing method provided in the embodiments of this application helps to achieve the purpose of irradiating nuclear fuel units 30 at different temperatures by placing different nuclear fuel units 30 into the first body 11 and the second body 12 respectively, and then setting the first body 11 and the second body 12 in different ways in the reactor channel 50.

[0070] The embodiments of this application also provide a nuclear fuel, which is prepared experimentally using the test methods of the embodiments of this application.

[0071] 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.

[0072] The above description is merely a specific embodiment 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. An irradiation testing apparatus suitable for testing the performance of nuclear fuel within the pores of a reactor, characterized in that, The irradiation testing apparatus includes: The device body is disposed within the ducts of the reactor. A containment assembly, configured to be inserted into or removed from the device body, is provided to contain multiple nuclear fuel units for performance testing. The device body and the containment assembly are configured such that: the device body is heated by a coolant within the channel, which transfers heat to the containment assembly, and the containment assembly transfers heat to the plurality of nuclear fuel units, and each of the nuclear fuel units is heated to a different temperature.

2. The apparatus according to claim 1, characterized in that, The device body has an inner wall and an outer wall, and is configured such that the inner wall forms a space, the space having the same length in a direction perpendicular to the inner wall; The receiving component is configured to be inserted into or removed from the space. The outer wall is in contact with the coolant, and the distance from the outer wall to the inner wall is different in the direction extending along the inner wall, so that each of the nuclear fuel units is heated to a different temperature.

3. The apparatus according to claim 2, characterized in that, The distance from the outer wall to the inner wall is the same within the range extending along the space in each of the nuclear fuel units, so that different parts of each nuclear fuel unit are heated to the same temperature.

4. The apparatus according to any one of claims 1-3, characterized in that, The containment assembly includes a containment component, a heat insulation component, and a push-pull component. Multiple nuclear fuel units are respectively disposed within different containment components, which are located within the device body. The heat insulation element is disposed between two adjacent receiving elements. The push-pull member is configured to be fixedly connected to the receiving member so that the receiving member can be placed into or removed from the device body.

5. The apparatus according to claim 1, characterized in that, The device body includes a first body and a second body, the first body forming an inner wall and an outer wall, and configured such that the inner wall forms a space having the same length in a direction perpendicular to the inner wall; the receiving component is disposed within the space, the outer wall is in contact with the coolant, and the outer wall is configured to extend at a different distance from the inner wall to the inner wall, so that each nuclear fuel unit is heated to a different temperature; The second body is configured to match the shape of the first body, and the second body can be disposed outside the first body so that the distance between the two can be adjusted, thereby adjusting the contact area between the coolant and the first body and the second body.

6. A method for determining the structural parameters of the device body of the apparatus according to any one of claims 1-5, wherein, The structural parameters of the device body include its inner diameter and its outer diameter, characterized in that the method includes the following steps: S10: Determine the first heat transfer coefficient between the receiving component and the inner wall of the device body; S20: Determine the second heat transfer coefficient between the outer wall of the device body and the coolant; S30: Determine the temperature of the device body, the temperature of the outer surface of the housing component, and the temperature of the coolant; S40: Determine the thermal conductivity, specific heat capacity, and density of the device body; S50: Based on the first heat transfer coefficient determined in step S10, the second heat transfer coefficient determined in step S20, the temperature of the device body determined in step S30, the temperature of the outer surface of the housing component and the temperature of the coolant, and the thermal conductivity, specific heat capacity and density of the device body determined in step S40, determine the inner diameter and outer diameter of the device body.

7. The method according to claim 6, characterized in that, In step S50, the inner diameter and the outer diameter of the device body satisfy the following expression: Where, ρ cd The density of the device body is represented by cd; cd represents the density of the device body; c pcd T represents the isobaric specific heat capacity of the device body; cd The temperature of the device body is represented by t; time is represented by r; distance is represented by λ. cd The thermal conductivity of the device body is represented by r. ci The inner diameter of the device body is represented by ci; the inner wall of the device body is represented by h. u,cd Represents the first heat transfer coefficient; u represents the housing component; T us The temperature of the outer surface of the housing component is indicated; us represents the outer wall of the housing component; r co The outer diameter of the device body is represented by 'co'; the outer wall of the device body is represented by 'h'. f,cd The second heat transfer coefficient is represented by f; the coolant is represented by T. f This indicates the temperature of the coolant.

8. A method for testing the performance of nuclear fuel, characterized in that, It includes the following steps: S1: Divide the nuclear fuel into multiple nuclear fuel units; S2: Place the nuclear fuel unit into the irradiation test apparatus according to any one of claims 1-5; S3: Simultaneously conduct irradiation tests on multiple nuclear fuel units at different temperatures.

9. The method according to claim 8, characterized in that, It also includes the following steps: S4: After steps S1-S3 are completed, the positions of the multiple nuclear fuel units within the irradiation test apparatus are moved, and the irradiation test is conducted again.

10. The method according to claim 8, characterized in that, It also includes the following steps: S5: Place different nuclear fuel units into the first and second bodies of the device body respectively; S6: The first body and the second body are arranged in different ways in the ducts of the reactor so that the nuclear fuel unit can be subjected to irradiation tests at different temperatures.

11. A nuclear fuel, characterized in that, The nuclear fuel is prepared experimentally by the method described in any one of claims 8-10.

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