Method and device for determining Doppler temperature coefficient

Abstract

The invention provides a Doppler temperature coefficient determination method and device, and relates to the technical field of nuclear power. The method comprises the steps that a moderator is controlled to change at a preset temperature change rate, and the temperature of fuel changes along with the temperature change of the moderator until the temperature of the fuel and the temperature of the moderator synchronously change at the temperature change rate; in the temperature change process, obtaining reactor core reactivity data of the nuclear reactor, and performing linear fitting on the reactor core reactivity data to obtain a reactivity change curve; determining a reactivity difference value between reactor core reactivity data and a reactivity change curve at the initial control moment of temperature change, and a temperature difference when the fuel and the moderator change synchronously; and determining the ratio of the reactivity difference to the temperature difference as the Doppler temperature coefficient of the fuel. The Doppler temperature coefficient of the fuel is obtained by using the temperature difference between the moderator and the fuel in the nuclear reactor and the reactivity difference value of the reactivity data of the reactor core, dependence on a theoretical value or an empirical value is not needed, the operation is convenient, and the coefficient precision is higher.

Description

Technical Field

[0001] The present disclosure relates to the field of nuclear power technology, and in particular to a method and device for determining a Doppler temperature coefficient. Background Art

[0002] The change in reactor reactivity caused by a 1°C change in the moderator temperature coefficient is the moderator temperature coefficient α. mod This parameter is crucial to the safety of the reactor. During the design process, it must meet the requirement of a negative value, that is, the increase in the moderator temperature will introduce negative reactivity, which will cause the reactor power to decrease and achieve reactor self-stability. After the reactor is loaded, the moderator temperature coefficient needs to be measured. The usual practice is to change the temperature of the moderator and fuel by breaking the thermal balance of the first and second loops before the nuclear heating point, and use a reactivity meter to measure the change in reactivity during the temperature change process. The ratio of the change in reactivity to the change in temperature is the isothermal temperature coefficient (the moderator temperature coefficient α mod +Fuel Doppler temperature coefficient α dop ), and then subtract the fuel Doppler temperature coefficient from the isothermal temperature coefficient to obtain the moderator temperature coefficient.

[0003] The change in reactor reactivity caused by a 1°C change in fuel temperature is the fuel Doppler temperature coefficient. Since the fuel temperature cannot be measured directly, the current fuel Doppler temperature coefficients are all theoretical values ​​or empirical values ​​given by program calculations. The accuracy of this value directly affects the measured value of the moderator temperature coefficient, which in turn affects the safety of the reactor. At the same time, the inaccuracy of the fuel Doppler temperature coefficient will also lead to inaccurate physical-thermal coupling during the development of nuclear design programs, thereby reducing the accuracy of program calculations. Summary of the invention

[0004] The present disclosure aims to solve one of the technical problems in the related art at least to some extent.

[0005] To this end, a first aspect of the present disclosure provides a method for determining a Doppler temperature coefficient, the method being applied to a nuclear reactor, the nuclear reactor comprising a fuel and a moderator, the method comprising the following steps:

[0006] Controlling the temperature of the moderator to change at a preset temperature change rate, the temperature of the fuel changes with the temperature change of the moderator, and when the temperature change time of the moderator exceeds a first time value, the temperature of the fuel changes synchronously with the temperature of the moderator at the temperature change rate;

[0007] Acquiring core reactivity data of the nuclear reactor during the temperature change of the moderator;

[0008] Performing linear fitting on the core reactivity data to obtain a reactivity change curve;

[0009] Determining a reactivity difference between the core reactivity data and the reactivity change curve at an initial control moment of temperature change;

[0010] Determine, based on the heat absorbed by the fuel per unit length according to the temperature change rate and a heat transfer equation, a temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate;

[0011] The ratio of the reactivity difference to the temperature difference is determined as the Doppler temperature coefficient of the fuel.

[0012] In some embodiments of the present disclosure, the heat absorbed by the fuel per unit length according to the temperature change rate is obtained by the following formula:

[0013] Φ=C*M*△t

[0014] Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and Δt is the temperature change rate.

[0015] In some embodiments of the present disclosure, the heat transfer equation is expressed as follows:

[0016] Φ=K*A*△T1

[0017] Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, A is the heat exchange area, and ΔT1 is the temperature difference.

[0018] In some embodiments of the present disclosure, the nuclear reactor is in a hot standby state and has not reached the nuclear heating point.

[0019] A second aspect of the present disclosure provides a device for determining a Doppler temperature coefficient, the device being applied to a nuclear reactor, the nuclear reactor comprising fuel and a moderator, the device comprising:

[0020] a temperature control module, configured to control the temperature of the moderator to change at a preset temperature change rate, the temperature of the fuel changes with the temperature change of the moderator, and when the temperature change time of the moderator exceeds a first time value, the temperature of the fuel changes synchronously with the temperature of the moderator at the temperature change rate;

[0021] A first acquisition module, used for acquiring the core reactivity data of the nuclear reactor during the temperature change of the moderator;

[0022] A second acquisition module is used to perform linear fitting on the core reactivity data to obtain a reactivity change curve;

[0023] A third acquisition module is used to determine the reactivity difference between the core reactivity data and the reactivity change curve at the initial control moment of the temperature change;

[0024] a fourth acquisition module, for determining, based on the heat absorbed by the fuel per unit length according to the temperature change rate and a heat transfer equation, a temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate;

[0025] A determination module is configured to determine a ratio of the reactivity difference to the temperature difference as a Doppler temperature coefficient of the fuel.

[0026] In some embodiments of the present disclosure, the fourth acquisition module is further used to obtain the amount of heat absorbed by the fuel per unit length according to the temperature change rate through the following formula:

[0027] Φ=C*M*△t

[0028] Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and Δt is the temperature change rate.

[0029] In some embodiments of the present disclosure, the heat transfer equation is expressed as follows:

[0030] Φ=K*A*△T1

[0031] Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, A is the heat exchange area, and ΔT1 is the temperature difference.

[0032] In some embodiments of the present disclosure, the nuclear reactor is in a hot standby state and has not reached the nuclear heating point.

[0033] A third aspect of the present disclosure provides an electronic device, comprising: a processor, and a memory communicatively connected to the processor;

[0034] The memory stores computer-executable instructions;

[0035] The processor executes the computer-executable instructions stored in the memory to implement the method described in the first aspect.

[0036] The fourth aspect of the present disclosure provides a computer-readable storage medium, characterized in that the computer-readable storage medium stores computer execution instructions, and when the computer execution instructions are executed by a processor, they are used to implement the method described in the first aspect.

[0037] The method for determining the Doppler temperature coefficient provided by the present disclosure uses the temperature difference between the moderator and the fuel in the nuclear reactor and the reactivity difference of the core reactivity data to obtain the fuel Doppler temperature coefficient, without relying on theoretical values ​​or empirical values, and is convenient to operate while having a higher coefficient accuracy. It indirectly improves the accuracy of the moderator temperature coefficient, ensures the safety of the nuclear reactor, and can also avoid, to a certain extent, the reduction in program calculation accuracy caused by inaccurate physical-thermal coupling during the development of nuclear design programs.

[0038] Additional aspects and advantages of the present disclosure will be given in part in the following description and in part will be obvious from the following description or learned through practice of the present disclosure. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] The above and / or additional aspects and advantages of the present disclosure will become apparent and easily understood from the following description of the embodiments in conjunction with the accompanying drawings, in which:

[0040] Figure 1 A schematic flow chart of a method for determining a Doppler temperature coefficient provided in an embodiment of the present disclosure;

[0041] Figure 2 A schematic diagram of controlling the temperature of the fuel and the temperature of the moderator to change synchronously at a temperature change rate provided by an embodiment of the present disclosure;

[0042] Figure 3 A schematic diagram of obtaining core reactivity data during a temperature change process of a moderator provided in an embodiment of the present disclosure;

[0043] Figure 4 A schematic diagram of a device for determining a Doppler temperature coefficient provided in an embodiment of the present disclosure. DETAILED DESCRIPTION

[0044] Embodiments of the present disclosure are described in detail below, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are intended to be used to explain the present disclosure, and should not be construed as limiting the present disclosure.

[0045] Specifically, the determination method and device of the Doppler temperature coefficient of the embodiment of the present disclosure are described below with reference to the accompanying drawings. The present disclosure relates to the field of nuclear power technology, and in particular to the field of nuclear power plants and research reactor technology.

[0046] Figure 1 The flowchart of a method for determining a Doppler temperature coefficient provided by an embodiment of the present disclosure is shown in FIG. It should be noted that the method is applied to a nuclear reactor, which includes fuel and a moderator. Figure 1As shown, the method for determining the Doppler temperature coefficient may include the following steps:

[0047] Step 101, controlling the temperature of the moderator to change at a preset temperature change rate, the temperature of the fuel changes with the temperature change of the moderator, and when the temperature change time of the moderator exceeds a first time value, the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate.

[0048] It should be noted that in some embodiments of the present disclosure, the nuclear reactor is in hot standby and has not reached the nuclear heating point, that is, the embodiments of the present disclosure are implemented before the reactor core heats up, and the fuel Doppler temperature coefficient is measured.

[0049] In one implementation, at the initial control time t1 of the temperature change, the initial temperature of the moderator and the initial temperature of the fuel are the same, both T1, and the core reactivity is ρ1. By breaking the thermal balance between the first and second loops, the temperature of the moderator in the first loop changes uniformly at a constant temperature change rate △t, and the moderator transfers heat to the fuel, so that the fuel temperature changes with the temperature of the moderator. Figure 2 A schematic diagram of controlling the temperature of the fuel and the temperature of the moderator to change synchronously at a temperature change rate provided by an embodiment of the present disclosure. Figure 2 Taking uniform heating as an example (the same is true for cooling analysis), Figure 2 It can be seen that the fuel temperature does not change at a uniform rate in the early stage, but after reaching a certain temperature difference with the moderator temperature or the temperature change time exceeds the first time value, the fuel and the moderator maintain the same temperature change rate △t and change synchronously.

[0050] Step 102, obtaining the core reactivity data of the nuclear reactor during the temperature change of the moderator.

[0051] In some embodiments of the present disclosure, the control time of the temperature of the fuel and the temperature of the moderator needs to be long enough, such as more than 15 minutes (the control time is only exemplary and does not limit the present solution, and can also be other control times, which are not limited to this). During the temperature change of the moderator, the core reactivity data of the nuclear reactor in the preset time period is obtained.

[0052] Figure 3 A schematic diagram of obtaining core reactivity data during a temperature change of a moderator provided in an embodiment of the present disclosure.

[0053] Step 103, performing linear fitting on the core reactivity data to obtain a reactivity variation curve.

[0054] Perform linear fitting on the core reactivity data to obtain the reactivity change curve:

[0055] ρ=k*t+b

[0056] Among them, ρ is the core reactivity data, and t is the control time of temperature change.

[0057] Step 104, determining the reactivity difference between the core reactivity data and the reactivity change curve at the initial control moment of the temperature change.

[0058] Determine the fitted core reactivity data *ρ1 corresponding to the initial control time t1 of the temperature change in the reactivity change curve. Determine the core reactivity data ρ1 actually obtained at the initial control time t1, and then determine the reactivity difference between the fitted core reactivity data *ρ1 and the core reactivity data ρ1:

[0059] Δρ=*ρ1-ρ1

[0060] Step 105, based on the heat absorbed by the fuel per unit length according to the temperature change rate and the heat transfer equation, determine the temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate.

[0061] The heat absorbed by the fuel per unit length according to the temperature change rate is obtained by the following formula:

[0062] Φ=C*M*△t

[0063] Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and △t is the temperature change rate.

[0064] Based on the heat absorbed by the fuel per unit length according to the temperature change rate obtained by the above formula, the temperature difference △T1 when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate is determined by the heat transfer equation. The formula of the heat transfer equation can be expressed as follows:

[0065] Φ=K*A*△T1

[0066] Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, which can be calculated according to the heat transfer model, A is the heat exchange area, which can be calculated by the geometric shape per unit length, and △T1 is the temperature difference.

[0067] In step 106, the ratio of the reactivity difference to the temperature difference is determined as the Doppler temperature coefficient of the fuel.

[0068] Due to the heat conduction between the moderator and the fuel, there is a temperature difference △T1 when the fuel and the moderator change synchronously, resulting in a reactivity difference Δρ between the actual core reactivity data and the fitted core reactivity data at the initial control time. Based on this principle, the fuel Doppler temperature coefficient can be obtained.

[0069] In some embodiments of the present disclosure, the fuel Doppler temperature coefficient can be accurately obtained by utilizing the temperature difference between the moderator and the fuel in the nuclear reactor and the reactivity difference of the core reactivity data, thereby improving the accuracy of the moderator temperature coefficient.

[0070] By implementing the disclosed embodiments, the fuel Doppler temperature coefficient is obtained by using the temperature difference between the moderator and the fuel in the nuclear reactor and the reactivity difference of the core reactivity data, without relying on theoretical values ​​or empirical values, and the operation is convenient and easy to promote, while the coefficient accuracy is higher. The accuracy of the moderator temperature coefficient is indirectly improved, the safety of the nuclear reactor is guaranteed, and the situation of reduced program calculation accuracy caused by inaccurate physical-thermal coupling during the development of nuclear design programs can be avoided to a certain extent.

[0071] Figure 4 Schematic diagram of a device for determining a Doppler temperature coefficient provided by an embodiment of the present disclosure. Figure 4 As shown, the device may include: a temperature control module 401 , a first acquisition module 402 , a second acquisition module 403 , a third acquisition module 404 , a fourth acquisition module 405 and a determination module 406 .

[0072] Among them, the temperature control module 401 is used to control the temperature of the moderator to change at a preset temperature change rate, and the temperature of the fuel changes with the temperature of the moderator. When the temperature change time of the moderator exceeds the first time value, the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate.

[0073] The first acquisition module 402 is used to acquire the core reactivity data of the nuclear reactor during the temperature change of the moderator.

[0074] The second acquisition module 403 is used to perform linear fitting on the core reactivity data to obtain a reactivity variation curve.

[0075] The third acquisition module 404 is used to determine the reactivity difference between the core reactivity data and the reactivity change curve at the initial control moment of the temperature change.

[0076] The fourth acquisition module 405 is used to determine the temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate according to the heat absorbed by the unit length of the fuel according to the temperature change rate and the heat transfer equation.

[0077] In some embodiments of the present disclosure, the fourth acquisition module 405 is further used to obtain the amount of heat absorbed by the fuel per unit length according to the temperature change rate through the following formula:

[0078] Φ=C*M*△t

[0079] Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and △t is the temperature change rate.

[0080] In some embodiments of the present disclosure, the heat transfer equation is expressed as follows:

[0081] Φ=K*A*△T1

[0082] Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, A is the heat exchange area, and △T1 is the temperature difference.

[0083] The determination module 406 is configured to determine the ratio of the reactivity difference to the temperature difference as the Doppler temperature coefficient of the fuel.

[0084] In some embodiments of the present disclosure, the nuclear reactor is in a hot standby state but has not reached the nuclear heating point.

[0085] Regarding the device in the above embodiment, the specific manner in which each module performs operations has been described in detail in the embodiment of the method, and will not be elaborated here.

[0086] In order to implement the above embodiments, the present disclosure also proposes an electronic device, including: a processor, and a memory communicatively connected to the processor; the memory stores computer-executable instructions; the processor executes the computer-executable instructions stored in the memory to implement the method provided by the above embodiments.

[0087] In order to implement the above embodiments, the present disclosure further proposes a computer-readable storage medium, in which computer-executable instructions are stored. When the computer-executable instructions are executed by a processor, they are used to implement the methods provided by the above embodiments.

[0088] In order to implement the above embodiments, the present disclosure also proposes a computer program product, including a computer program, which implements the methods provided by the above embodiments when executed by a processor.

[0089] In the description of the aforementioned embodiments, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of the different embodiments or examples, unless they are contradictory.

[0090] In addition, the terms "first" and "second" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of the features. In the description of the present disclosure, "plurality" means at least two, such as two, three, etc., unless otherwise clearly and specifically defined.

[0091] Any process or method description in a flowchart or otherwise described herein may be understood to represent a module, segment or portion of code that includes one or more executable instructions for implementing the steps of a custom logical function or process, and the scope of the preferred embodiments of the present disclosure includes additional implementations in which functions may not be performed in the order shown or discussed, including performing functions in a substantially simultaneous manner or in reverse order depending on the functions involved, which should be understood by technicians in the technical field to which the embodiments of the present disclosure belong.

[0092] The logic and / or steps represented in the flowchart or otherwise described herein, for example, can be considered as an ordered list of executable instructions for implementing logical functions, and can be embodied in any computer-readable medium for use by an instruction execution system, device or apparatus (such as a computer-based system, a system including a processor, or other system that can fetch instructions from an instruction execution system, device or apparatus and execute the instructions), or in combination with these instruction execution systems, devices or apparatuses. For the purpose of this specification, "computer-readable medium" can be any device that can contain, store, communicate, propagate or transmit a program for use by an instruction execution system, device or apparatus, or in combination with these instruction execution systems, devices or apparatuses. More specific examples of computer-readable media (a non-exhaustive list) include the following: an electrical connection with one or more wires (electronic device), a portable computer disk box (magnetic device), a random access memory (RAM), a read-only memory (ROM), an erasable and programmable read-only memory (EPROM or flash memory), a fiber optic device, and a portable compact disk read-only memory (CDROM). In addition, the computer-readable medium may even be paper or other suitable medium on which the program is printed, since the program may be obtained electronically, for example, by optically scanning the paper or other medium and then editing, interpreting or processing in other suitable ways if necessary, and then stored in a computer memory.

[0093] It should be understood that the various parts of the present disclosure can be implemented in hardware, software, firmware or a combination thereof. In the above-mentioned embodiments, multiple steps or methods can be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, any one of the following technologies known in the art or a combination thereof can be used to implement: a discrete logic circuit having a logic gate circuit for implementing a logic function for a data signal, a dedicated integrated circuit having a suitable combination of logic gate circuits, a programmable gate array (PGA), a field programmable gate array (FPGA), etc.

[0094] A person skilled in the art may understand that all or part of the steps in the method for implementing the above-mentioned embodiment may be completed by instructing related hardware through a program, and the program may be stored in a computer-readable storage medium, which, when executed, includes one or a combination of the steps of the method embodiment.

[0095] In addition, each functional unit in each embodiment of the present disclosure may be integrated into a processing module, or each unit may exist physically separately, or two or more units may be integrated into one module. The above-mentioned integrated module may be implemented in the form of hardware or in the form of a software functional module. If the integrated module is implemented in the form of a software functional module and sold or used as an independent product, it may also be stored in a computer-readable storage medium.

[0096] The storage medium mentioned above may be a read-only memory, a disk or an optical disk, etc. Although the embodiments of the present disclosure have been shown and described above, it can be understood that the above embodiments are exemplary and cannot be understood as limitations of the present disclosure. A person of ordinary skill in the art may change, modify, replace and modify the above embodiments within the scope of the present disclosure.

Claims

1. A method for determining a Doppler temperature coefficient, the method being applied to a nuclear reactor, the nuclear reactor comprising a fuel and a moderator, characterized in that: The method comprises the following steps: Controlling the temperature of the moderator to change at a preset temperature change rate, the temperature of the fuel changes with the temperature change of the moderator, and when the temperature change time of the moderator exceeds a first time value, the temperature of the fuel changes synchronously with the temperature of the moderator at the temperature change rate; Acquiring core reactivity data of the nuclear reactor during the temperature change of the moderator; Performing linear fitting on the core reactivity data to obtain a reactivity change curve; Determining a reactivity difference between the core reactivity data and the reactivity change curve at an initial control moment of temperature change; Determine, based on the heat absorbed by the fuel per unit length according to the temperature change rate and a heat transfer equation, a temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate; The ratio of the reactivity difference to the temperature difference is determined as the Doppler temperature coefficient of the fuel.

2. The method according to claim 1, characterized in that: The heat absorbed by the fuel per unit length according to the temperature change rate is obtained by the following formula: Φ=C*M*△t Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and Δt is the temperature change rate.

3. The method according to claim 1 or 2, characterized in that: The heat transfer equation is formulated as follows: Φ=K*A*△T1 Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, A is the heat exchange area, and ΔT1 is the temperature difference.

4. The method according to claim 1, characterized in that: The nuclear reactor is in a hot standby state and has not reached the nuclear heating point.

5. A device for determining a Doppler temperature coefficient, the device being applied to a nuclear reactor, the nuclear reactor comprising a fuel and a moderator, characterized in that: The device comprises: a temperature control module, configured to control the temperature of the moderator to change at a preset temperature change rate, the temperature of the fuel changes with the temperature change of the moderator, and when the temperature change time of the moderator exceeds a first time value, the temperature of the fuel changes synchronously with the temperature of the moderator at the temperature change rate; A first acquisition module is used to acquire the core reactivity data of the nuclear reactor during the temperature change of the moderator; A second acquisition module is used to perform linear fitting on the core reactivity data to obtain a reactivity change curve; A third acquisition module is used to determine the reactivity difference between the core reactivity data and the reactivity change curve at the initial control moment of the temperature change; a fourth acquisition module, for determining, based on the heat absorbed by the fuel per unit length according to the temperature change rate and a heat transfer equation, a temperature difference when the temperature of the fuel and the temperature of the moderator change synchronously at the temperature change rate; A determination module is configured to determine a ratio of the reactivity difference to the temperature difference as a Doppler temperature coefficient of the fuel.

6. The device according to claim 5, characterized in that The fourth acquisition module is further used to obtain the amount of heat absorbed by the fuel per unit length according to the temperature change rate through the following formula: Φ=C*M*△t Among them, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, C is the specific heat capacity of the fuel, M is the mass of the fuel per unit length, and Δt is the temperature change rate.

7. The device according to claim 5 or 6, characterized in that The heat transfer equation is formulated as follows: Φ=K*A*△T1 Wherein, Φ is the heat absorbed by the fuel per unit length according to the temperature change rate, K is the heat transfer coefficient, A is the heat exchange area, and ΔT1 is the temperature difference.

8. The device according to claim 5, characterized in that The nuclear reactor is in a hot standby state and has not reached the nuclear heating point.

9. An electronic device, characterized in that: include: A processor, and a memory communicatively connected to the processor; The memory stores computer-executable instructions; The processor executes the computer-executable instructions stored in the memory to implement the method according to any one of claims 1 to 4.

10. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores computer-executable instructions, which are used to implement the method according to any one of claims 1 to 4 when executed by a processor.

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