Heat pipe heat transfer performance test method, electronic equipment and test system
By establishing a heat source simulation model, combining neutron dynamics and thermal power feedback mechanisms, the problems of low efficiency and high cost of the existing heat pipe heat transfer performance testing methods are solved, and efficient testing and verification of heat pipes under nuclear heating conditions are achieved, reducing R&D costs and cycles.
Patent Information
- Application Number
- CN202510636983.6
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-05-19
- Publication Date
- 2025-08-22
AI Technical Summary
The existing heat transfer performance testing methods of heat pipes cannot efficiently verify the compliance of technical indicators of heat pipes in nuclear power systems, and the traditional methods are costly and work-intensive, making it difficult to meet the needs of design verification.
The heat transfer performance test method based on the simulation model is adopted, combined with neutron dynamics and thermal power feedback mechanisms, a heat source simulation model is established, and the heat transfer condition of the heat pipe under the nuclear heating conditions is calculated through multi-physical coupled simulation, and the heat flow loading capacity is calculated based on the actual measured temperature.
It has achieved efficient verification of the transient operating characteristics and performance indicator compliance of the heat pipe, reduced R&D costs and cycles, and improved testing accuracy and efficiency.
Smart Images
Figure CN120524686A_ABST
Abstract
Description
Technical Field
[0001] The present application belongs to the field of heat pipe testing technology, and in particular relates to a heat pipe heat transfer performance testing method, electronic equipment, and testing system. Background Art
[0002] Heat pipes offer the advantages of being passive, offering high heat flux, minimal temperature drop, and being safe and reliable. Heat pipe reactor power systems using them as heat transfer components have great potential for application on land, at sea, in the air, and in space. When developing the heat pipe products required for such systems, it is necessary to verify whether they meet the corresponding heat transfer performance specifications under the system's nuclear heating conditions. In principle, the most direct verification method is to conduct system integration coupling tests, but this is costly and labor-intensive, and the progress of heat pipe verification may be constrained by the research and development of other functional components and interfaces.
[0003] Traditional heat pipe heat transfer performance tests are mainly used to carry out performance tests under simplified heating modes. They are suitable for general heat transfer law / mechanism research and model verification, and cannot directly verify the technical indicator compliance of heat pipe products in nuclear power systems. In addition, the existing heat pipe heat transfer performance test methods are mainly physical operation methods, but there is currently no test method based on simulation models, which cannot efficiently verify the performance of heat pipes. In addition, a few literatures have reported on simulated nuclear heating coupling test devices using resistance heating elements (such as Sun Xingang et al., Transient Characteristics Analysis of Heat Pipe Reactor Core Scaled Module, Atomic Energy Science and Technology, Vol. 55, No. 10, 2021). These devices have the disadvantages of limited heating capacity of resistance heating elements and difficulty in achieving an efficient heat transfer interface between heating elements and high-temperature heat pipes. It is difficult to apply the large heat flux load required for design verification to the heat pipe. Summary of the Invention
[0004] The present application aims to at least to some extent solve the technical problem of not being able to efficiently verify the performance of heat pipes. To this end, the present application provides a heat pipe heat transfer performance test method, electronic equipment and test system, which can simulate the heat transfer of heat pipes under nuclear heating conditions, and efficiently verify whether the heat pipes meet the corresponding performance technical index requirements, which helps to understand the transient and steady-state operating characteristics and index compliance of the heat pipes, and realize efficient testing research and verification to support design and verification, thereby enabling rapid iteration and greatly reducing R&D costs and cycles.
[0005] In a first aspect, an embodiment of the present application provides a method for testing the heat transfer performance of a heat pipe, which is applied to a heat pipe. One end of the heat pipe is heated by an induction coil, and the other end exchanges heat with a cold source. The heat transfer performance testing method of the heat pipe includes:
[0006] Combining neutron dynamics with thermal power feedback mechanisms, a differential equation for the time-varying fission power of the reactor is established;
[0007] Establish a differential equation for the time-varying concentration of delayed neutron precursor nuclei;
[0008] An equation for the total reactivity is established based on the initial reactivity, the reactivity introduced by external control, and the temperature feedback effect;
[0009] According to the heat transfer model of the simulated nuclear power system, the relationship between the heat flux to be loaded into the heat pipe and the reactor fission power and heat pipe temperature is established;
[0010] The above equations and relationships are combined to establish a heat source simulation model, and the measured temperature of the heat pipe is substituted to obtain the heat flow that should be loaded into the heat pipe.
[0011] In some embodiments, the differential equation for the change in reactor fission power over time is:
[0012]
[0013] Among them, Q fiss is the reactor fission power; ρ is the total reactivity; β is the total fraction of delayed neutrons, β i is the delayed neutron fraction of group i; Λ is the neutron generation time; λ i is the decay constant of the delayed neutron precursor nucleus of group i; C i is the concentration of the i-th group of delayed neutron precursor nuclei; S0 is the neutron source; N is the total number of delayed neutron precursor nuclei; i is the group number of the delayed neutron precursor nuclei.
[0014] In some embodiments, the differential equation for the time-varying concentration of delayed neutron precursors is:
[0015]
[0016] Among them, C i is the concentration of delayed neutron precursor nuclei in group i; β i is the delayed neutron fraction of group i; Λ is the neutron generation time; Q fiss is the reactor fission power; i is the decay constant of the delayed neutron precursor nucleus of group i.
[0017] In some embodiments, the equation for overall reactivity is:
[0018] ρ=ρ0+ρ ext +α Fuel (T Fuel -T0)+α HP (T HP -T0)+α other (T other -T0)
[0019] Where ρ is the total reactivity; ρ0 is the initial reactivity, representing the intrinsic reactivity of the core at the reference temperature; ρ ext is the external control reactivity; α Fuel is the fuel reactivity temperature coefficient; α HP is the heat pipe reactivity temperature coefficient; α other is the reactivity temperature coefficient of other reactor components; T Fuel is the calculated value of nuclear fuel temperature, T other is the calculated temperature of other reactor components; T HP is the measured temperature of the heat pipe; T0 is the reference temperature.
[0020] In some embodiments, the calculated nuclear fuel temperature T Fuel , calculated temperature values of other reactor components T other Determined by the heat transfer model of the nuclear power system being simulated.
[0021] In some embodiments, the method further includes converting the induced heat of the heat pipe to the current in the coil, and establishing a conversion model between the current in the induction coil and the temperature of the heat pipe through multi-physics simulation calculation results.
[0022] In some embodiments, a temperature correction for the heating heat flow is introduced, and the conversion model is:
[0023] Q HP-ref =AI 2 +BI+C
[0024] K=EI 2 +FI+G
[0025] Q HP =Q HP-ref +K(T HP -T HP -ref)
[0026] Where I is the current in the induction coil; T HP-ref is the temperature of the heat pipe under reference operating conditions; Q HP-ref The heat pipe temperature is T HP-ref , the induced heat flux input to the heat pipe when the induction coil is loaded with a current of I; K is the temperature correction coefficient of the heating heat flux; Q HP is the heat flux to be loaded into the heat pipe; A, B, C, E, F, and G are coefficients, which are determined by multi-physics simulation results or calibration test fitting.
[0027] In some embodiments, the heat transfer flow of the heat pipe at the cold source is calculated, and a heat transfer formula is established for calculation based on the mass flow rate of the working fluid in the cold source and the temperature at the inlet and outlet of the cold source.
[0028] In a second aspect, an embodiment of the present application provides an electronic device comprising a memory, a processor, and a computer program stored in the memory and executable in the processor. When the computer program is executed, the steps corresponding to the above-mentioned heat pipe heat transfer performance test method are performed.
[0029] In a third aspect, an embodiment of the present application provides a testing system that employs the above-mentioned heat pipe heat transfer performance testing method. The testing system includes:
[0030] The heat pipe is divided into a heating section, a middle section and a heat exchange section along its length, and the middle section is coated with a heat insulating material;
[0031] The induction coil is arranged in the heating section of the heat pipe and is used to heat the heating section of the heat pipe;
[0032] An alternating current source, connected to the induction coil to form a loop, is used to regulate the current I;
[0033] Heat pipe temperature measurement module, used to measure the actual temperature T of the heating section HP , so that the heat source simulation model obtains the input value;
[0034] At least two working fluid temperature measurement modules are placed at the inlet and outlet of the cold source, respectively, to measure the inlet temperature t of the cold source. i , outlet temperature t o ; Among them, a pipeline is connected between the inlet and outlet of the cold source; a flow measurement module, a valve and a refrigeration device are provided on the pipeline;
[0035] Electronic equipment used to collect data from the heat pipe temperature measurement module, alternating current source, working fluid temperature measurement module, and flow measurement module, so as to calculate the heating heat flow of the heat pipe and the current of the induction coil based on the data and the heat source simulation model.
[0036] It can be seen from the above technical solution that the beneficial effects of this application are:
[0037] 1. The test method of this application establishes a heat source simulation model by coupling multiple parameters, thereby realizing closed-loop simulation of fission power, reactivity, and heat flow of heat pipes. Through the coupling relationship of the differential equation of the reactor fission power changing with time, the differential equation of the delayed neutron precursor nuclear concentration changing with time, and the equation of total reactivity, the heat transfer of the heat pipe under nuclear heating conditions is accurately simulated. Combined with the measured temperature of the heat pipe, the expected reactor nuclear fission power is calculated, and then the heat flow to be loaded into the heat pipe can be solved, and whether the heat pipe meets the corresponding performance technical indicator requirements can be efficiently verified, which helps to understand the transient and steady-state operating characteristics and indicator compliance of the heat pipe, and realize efficient testing research and verification to support design and verification, thereby enabling rapid iteration and greatly reducing R&D costs and cycles.
[0038] 2. The electronic device of this application, through the collaboration of software and hardware, writes the heat pipe heat transfer performance test method into a computer program. Through the automated calculation of the computer program, memory and processor, it significantly improves the test accuracy and efficiency, and can significantly reduce energy consumption and labor costs, providing key support for heat pipe selection and reliability evaluation.
[0039] 3. The test system of this application is suitable for the entire process from test operation, data collection, test verification to heat dissipation optimization. The current in the induction coil is regulated by an alternating current source, the heating section of the heat pipe is heated by the induction coil, and the external heat transfer between the heating section and the heat exchange section is isolated by thermal insulation materials, thereby realizing the heat pipe test under standard nuclear heating conditions. The working fluid temperature measurement module, flow measurement module, etc. are used to provide conditions for monitoring the working fluid state of the cold source. In this way, multiple data can be collected by electronic equipment, thereby providing a basis for analyzing and judging the performance of the heat pipe. This application can create simulated nuclear heating boundary conditions for the heat pipe before conducting a real system-level integrated coupling test, and can accurately calculate the heat flow of the heat pipe under the expected nuclear heating conditions without relying on other functions, thereby realizing efficient testing research and verification. BRIEF DESCRIPTION OF THE DRAWINGS
[0040] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following will briefly introduce the drawings required for use in the description of the embodiments. Obviously, the drawings described below are some embodiments of the present application. For ordinary technicians in this field, other embodiments and drawings can be obtained based on these drawings without creative work. The flowcharts shown in the drawings are only exemplary illustrations and do not necessarily include all the content and operations / steps, nor do they have to be executed in the order described. For example, some operations / steps can be decomposed, while some operations / steps can be combined or partially combined, so the actual execution order may change according to the actual situation.
[0041] Figure 1 A schematic diagram of an embodiment of a test system of the present invention is shown;
[0042] Figure numerals: 100, test system; 110, heat pipe; 111, heating section; 112, middle section; 113, heat exchange section; 120, induction coil; 130, alternating current source; 140, heat pipe temperature measurement module; 150, electronic equipment; 160, working fluid temperature measurement module; 170, calorimetric heat exchanger; 180, flow measurement module; 190, refrigeration device; 191, valve; 200, thermal insulation material. DETAILED DESCRIPTION
[0043] The following will be combined with the accompanying drawings corresponding to the specific embodiments of the present application to clearly and completely describe the technical solutions in the embodiments of the present application. The following detailed description of the embodiments of the present application provided in the accompanying drawings is not intended to limit the scope of the present application for protection. The described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, various different configurations can be arranged and designed. All other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application.
[0044] The present application is described below with reference to specific embodiments and with reference to the accompanying drawings:
[0045] In a first aspect of the present application, an embodiment provides a heat pipe heat transfer performance testing method, which is applied to a heat pipe to test the performance of the heat pipe, such as the heat flow to be loaded to the heat pipe, the conversion of the heat flow to be loaded to the induction coil current, the transmission of heat flow to the cold source, etc. One end of the heat pipe is heated by the induction coil, and the other end exchanges heat with the cold source to test the directional heat transfer process achieved by the phase change cycle of the working fluid inside the heat pipe. The heat pipe heat transfer performance testing method includes:
[0046] S1. Combining neutron dynamics with the thermal power feedback mechanism, a differential equation is established to describe the time-varying behavior of the reactor fission power. This equation can describe the transient variation of the reactor fission thermal power. The thermal power feedback mechanism considers the effect of temperature on reactivity and the effect of heat pipe heat dissipation. Establishing this equation can comprehensively consider system characteristics such as neutron physics and thermal power feedback.
[0047] S2. Establish a differential equation for the time-varying concentration of delayed neutron precursor nuclei in the reactor. This equation can describe the temporal variation of the delayed neutron precursor nuclei concentration in the reactor, characterize the dynamic equilibrium of the delayed neutron precursor nuclei, and can be used to establish a simulation model.
[0048] S3. Based on the initial reactivity, the reactivity introduced by external control, and the temperature feedback effect, an equation for the total reactivity is established. By integrating the coupling effects related to multiple reactivities, the total reactivity of the reactor can be described, reflecting the influence of multiple parameters on the reactivity, and ensuring safety and stability.
[0049] S4. Based on the heat transfer model of the simulated nuclear power system, establish the relationship between the heat flux to be loaded into the heat pipe, the reactor fission power, and the heat pipe temperature; by dynamically coupling the reactor fission power with the heat pipe heat transfer parameters, achieve accurate prediction of the heat pipe heat flux, and transform the complex problem of heat transfer into a quantifiable process.
[0050] S5. A heat source simulation model is established by combining the above equations and relationships, and the measured temperature of the heat pipe is substituted to obtain the heat flux that should be loaded into the heat pipe; by combining the various equations of S1-S4, a heat source simulation model with the action of multiple physical fields is established. In this way, the expected nuclear fission power of the reactor can be calculated through the measured heat pipe temperature, and the heat flux that should be loaded into the heat pipe can be directly obtained.
[0051] The testing methods of the existing technology are mainly physical operation methods. There is currently no testing method based on simulation models, which cannot efficiently verify the performance of heat pipes. However, this application couples multiple parameters to establish a heat source simulation model, realizing closed-loop simulation of fission power, reactivity, and heat flow of heat pipes. Through the coupling relationship of the differential equation of reactor fission power changing with time, the differential equation of delayed neutron precursor nuclear concentration changing with time, and the equation of total reactivity, the heat transfer of the heat pipe under nuclear heating conditions is accurately simulated. Combined with the measured temperature of the heat pipe, the expected reactor nuclear fission power is calculated, and then the heat flow to be loaded into the heat pipe can be solved, and whether the heat pipe meets the corresponding performance technical index requirements can be efficiently verified. It helps to understand the transient and steady-state operating characteristics and index compliance of the heat pipe, realize efficient testing research and verification, support design and verification, and thus enable rapid iteration, greatly reducing R&D costs and cycles.
[0052] In some embodiments, the differential equation for the change in reactor fission power over time is:
[0053]
[0054] Among them, Q fiss is the reactor fission power; ρ is the total reactivity; β is the total fraction of delayed neutrons, β i is the delayed neutron fraction of group i; Λ is the neutron generation time; λ i is the decay constant of the delayed neutron precursor nucleus of group i; C i is the concentration of the i-th group of delayed neutron precursor nuclei; S0 is the neutron source; N is the total number of delayed neutron precursor nuclei; i is the group number of the delayed neutron precursor nuclei.
[0055] In some embodiments, the differential equation for the time-varying concentration of delayed neutron precursors is:
[0056]
[0057] Among them, C i is the concentration of delayed neutron precursor nuclei in group i; β i is the delayed neutron fraction of group i; Λ is the neutron generation time; Q fiss is the reactor fission power; i is the decay constant of the delayed neutron precursor nucleus of group i.
[0058] In some embodiments, the equation for overall reactivity is:
[0059] ρ=ρ0+ρ ext +α Fuel (T Fuel -T0)+α HP (T HP -T0)+α other (T other -T0) (3)
[0060] Where ρ is the total reactivity; ρ0 is the initial reactivity, representing the intrinsic reactivity of the core at the reference temperature; ρ ext is external control responsiveness; α Fuel is the fuel reactivity temperature coefficient; α HP is the heat pipe reactivity temperature coefficient; α other is the reactivity temperature coefficient of other reactor components; T Fuel is the calculated value of nuclear fuel temperature, T other is the calculated temperature of other reactor components; T HP is the measured temperature of the heat pipe; T0 is the reference temperature.
[0061] In some embodiments, the calculated nuclear fuel temperature T Fuel , calculated temperature values of other reactor components T other Determined by the heat transfer model of the simulated nuclear power system, involving the heat transfer inside and at the interface of nuclear fuel, heat pipes and other components, the heat transfer model is as follows:
[0062] T Fuel =f(Q fiss ,T HP ) (4)
[0063] T other =φ(Q fiss ,T HP ) (5)
[0064] Wherein, f and φ are both heat transfer models of the simulated nuclear power system. In an optional embodiment, the relationship between the heat flux to be loaded into the heat pipe and the reactor fission power and the heat pipe temperature is established and determined using the following formula:
[0065] Q HP =g(Q fiss ,T HP ) (6)
[0066] Among them, Q HPis the heat flux to be loaded into the heat pipe; ɡ is the heat transfer model of the simulated nuclear power system, which also involves the heat transfer inside and at the interfaces of nuclear fuel, heat pipes and other components. The heat transfer model is determined based on the system and is the existing technology in this field.
[0067] In some embodiments, the method further includes converting the induced heat of the heat pipe to the current in the coil, and establishing a conversion model between the current in the induction coil and the temperature of the heat pipe through multi-physics simulation calculation results.
[0068] In some embodiments, a temperature correction for the heating heat flow is introduced, and the conversion model is:
[0069] Q HP-ref =AI 2 +bI+C (7)
[0070] K=EI 2 +FI+G (8)
[0071] Q HP =Q HP-ref +K(T HP -T HP-ref ) (9)
[0072] Where I is the current in the induction coil; T HP-ref is the temperature of the heat pipe under reference operating conditions; Q HP-ref The heat pipe temperature is T HP-ref , the induced heat flux input to the heat pipe when the induction coil is loaded with a current of I; K is the temperature correction coefficient of the heating heat flux; Q HP is the heat flux to be loaded into the heat pipe; A, B, C, E, F, and G are all coefficients (e.g., A=0.01, B=-0.5, C=20, E=10, F=-15, G=2300), which are determined by multi-physics simulation calculation results or calibration test fitting.
[0073] In some embodiments, the heat transfer flux of the heat pipe at the cold source is calculated by establishing a heat transfer formula based on the mass flow rate of the working fluid in the cold source and the temperature at the cold source inlet and outlet. Specifically, the heat exchange section of the heat pipe uses a calorimetric heat exchanger for condensation, and the cold source is provided by the calorimetric heat exchanger. The inlet and outlet of the calorimetric heat exchanger are connected by a pipe. The heat transfer flux at the cold source is expressed as:
[0074] Q c =mc(t o -t i ) (10)
[0075] Where m is the mass flow rate of the cooling medium in the calorimetric heat exchanger, c is the specific heat of the cooling medium, t i is the temperature of the cooling medium at the inlet of the heat exchanger, t ois the temperature of the cooling medium at the outlet of the heat exchanger.
[0076] The second embodiment of the present application provides an electronic device, including a memory, a processor, and a computer program stored in the memory and executable in the processor. When the computer program is executed, it performs the steps corresponding to the above-mentioned heat pipe heat transfer performance test method. When the processor executes the computer program, it implements the steps in the above-mentioned method embodiment. It should be understood that the electronic devices of each embodiment of the present application can be implemented based on a memory and a processor, each memory being used to store a computer program for executing the above-mentioned method of the present application, and the processor executing the above-mentioned computer program so that the electronic device implements the method of each of the above-mentioned embodiments.
[0077] In some embodiments, the computer program is divided into a heat source simulation module and an induction heat and current conversion module, wherein the heat source simulation module includes the above steps S1-S5, and the method or process exemplified in the S1-S5 implementation mode, which is used to set the reactor kinetic parameters and reactivity hourly loading curve of the reactor design to be verified, and calculate the expected reactor nuclear fission power in combination with the measured heat pipe temperature data, thereby obtaining the heat flux to be loaded to the heat pipe; and the induction heat and current conversion module is used to realize the heat flux Q to be loaded to the heat pipe. HP The current conversion calculation of the induction coil should be loaded, and the specific calculation is as shown in the conversion model above.
[0078] In some embodiments, the electronic device may be a desktop computer, a notebook computer, an industrial computer, a PDA, a tablet computer or other mobile terminal, as well as a computer device such as a cloud server, and is not limited to any operating system. Figure 1 The examples of electronic devices do not constitute a limitation of the electronic devices, and may include more or fewer components than shown in the figures, or a combination of certain components, or different components. For example, the electronic device may also include input devices, output devices, network access devices, buses, etc.
[0079] The electronic device of the present application, through the collaboration of software and hardware, writes the heat pipe heat transfer performance test method into a computer program. Through the automated calculation of the computer program, memory and processor, the test accuracy and efficiency are significantly improved, while energy consumption and labor costs can be significantly reduced, providing key support for heat pipe selection and reliability assessment. At the same time, the test method is modularized to set the reactor kinetic parameters and reactivity hourly loading curve of the reactor design to be verified, so that the results can be directly output in combination with the measured heat pipe temperature.
[0080] Please refer to Figure 1The third embodiment of the present application provides a test system that adopts the above-mentioned heat pipe heat transfer performance test method. The test system includes: a heat pipe, an induction coil, an alternating current source, a heat pipe temperature measurement module, a working fluid temperature measurement module and an electronic device. The heat pipe adopts a sample in the shape of a long rod, which is the object to be tested. The heat pipe is divided into a heating section, an intermediate section and a heat exchange section along the length direction, which is basically equally divided by length as shown in the figure. The intermediate section is coated with a thermal insulation material. The intermediate section is located between the heating section and the heat exchange section. The thermal insulation material coated on the outside of the intermediate section serves as a thermal insulation member. The thermal insulation material includes thermal insulation cotton, graphite felt, multi-layer metal foil, etc. The thermal insulation member is used to suppress heat leakage in the intermediate section and the heat exchange section; the induction coil is arranged in the heating section of the heat pipe to heat the heating section, specifically to generate an alternating electromagnetic field and then excite induced heat on the heating section of the heat pipe. The induction coil is spirally arranged at intervals in the circumference of the heating section; the alternating current source is connected to the induction coil to form a loop, which is used to regulate the current I, and the regulated current can be displayed. The displayed value can be regarded as the actual measured value of the current. The alternating current source, such as a programmable alternating current source, specifically provides a modulated alternating current to the induction coil.
[0081] The heat pipe temperature measurement module can use conventional devices for measuring temperature to measure the actual temperature T of the heating section. HP , so that the above heat source simulation model obtains the substitution value; at least two working fluid temperature measurement modules are placed at the inlet and outlet of the cold source respectively, such as a working fluid temperature measurement module is installed at the inlet and outlet respectively, respectively for measuring the inlet temperature t of the cold source i , outlet temperature t o The working fluid temperature measurement module adopts a thermometer or other temperature measuring instrument; wherein, a pipeline is connected between the inlet and outlet of the cold source; a flow measurement module, a valve and a refrigeration device are provided on the pipeline, the flow measurement module adopts a flow meter or a conventional measuring instrument, and the flow rate of the cooling working fluid is measured by the flow measurement module, the valve adopts a manual, pneumatic, electric or other conventional valve, and the flow rate of the cooling working fluid is adjusted by the valve, the refrigeration device adopts a conventional refrigeration device, and the working fluid is cooled and stored by the refrigeration device; the electronic equipment is used to collect data from the heat pipe temperature measurement module, the alternating current source, the working fluid temperature measurement module, and the flow measurement module, so as to calculate the heating heat flow of the heat pipe and the current of the induction coil based on the data and the heat source simulation model, and the electronic equipment is electrically connected to the above modules or power supplies respectively, and a wireless communication connection method can also be adopted.
[0082] This application is applicable to the entire process from experimental operation, data collection, test verification to heat dissipation optimization. The current in the induction coil is regulated by an alternating current source, the heating section of the heat pipe is heated by the induction coil, and the external heat transfer between the heating section and the heat exchange section is isolated by thermal insulation materials, thereby realizing the heat pipe test under standard nuclear heating conditions. The working fluid temperature measurement module, flow measurement module, etc. are used to provide conditions for monitoring the working fluid state of the cold source. In this way, multiple data can be collected by electronic equipment, thereby providing a basis for analyzing and judging the performance of the heat pipe. This application can create simulated nuclear heating boundary conditions for the heat pipe before conducting a real system-level integrated coupling test, and can accurately calculate the heat flow of the heat pipe under the expected heating conditions without relying on other functions, thereby realizing efficient testing, research and verification.
[0083] In some embodiments, the electronic device further includes a memory, a processor, and a computer program stored in the memory and executable on the processor. The computer program can also be used to generate the required real-time induced current control signal to control the heating power based on the heat pipe temperature data, cooling heat flow data, and embedded heating simulation software. The heat source simulation module in the computer program can be implemented based on the model of formulas (1) to (6), or based on a deterministic neutron transport model, or based on a random neutron transport model; the induced heat and current conversion module can be implemented based on the model of formulas (7) to (9), or based on a real-time induction heating multi-physics simulation model.
[0084] In some embodiments, the heat pipe can be a pipe filled with lithium, sodium, potassium, rubidium, cesium, mercury, water and other working fluids, or it can be a loop pipe circulating lithium, sodium, potassium, rubidium, cesium, mercury, water and other working fluids; in some embodiments, the alternating current source can be medium or low frequency or high frequency, with a frequency coverage range of 1kHz to 1000kHz; the heat pipe temperature measurement module can use a thermocouple, platinum resistance, or fiber optic thermometer that is mechanically fastened, bonded or welded to the surface of the heat pipe for contact temperature measurement, or it can use an infrared thermometer or thermal imager for non-contact temperature measurement of the surface of the heat pipe sample.
[0085] In some embodiments, the above-mentioned cold source can use a calorimetric heat exchanger to realize the heat exchange function between the heat pipe and the internal cooling medium, and the cooling medium can be gas, liquid, solid heat conduction heat exchange, or radiation heat exchange, and the heat exchange method can be gas or liquid convection heat exchange.
[0086] Regarding the specific implementation of this application, it should be noted that:
[0087] In the description of this application, the terms "comprises," "includes," or any other variations thereof are intended to encompass non-exclusive inclusion, such that a process, method, apparatus, or readable storage medium comprising a series of elements includes not only those elements but also other elements not explicitly listed that are consistent with the concept of this application, or elements inherent to such process, method, apparatus, or readable storage medium. In the absence of further limitations, an element defined by the phrase "comprising a ..." does not exclude the presence of additional elements in the process, method, apparatus, or readable storage medium comprising the element.
[0088] In the description of this application, reference to the terms "some embodiments", "optional embodiments", "examples", "specific examples", "optional examples" or "optional embodiments" and the like 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 this application, but does not mean that these embodiments illustrate and describe all possible forms of the invention. 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 suitable manner in any one or more embodiments or examples. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification.
[0089] The present invention has been described in detail above with reference to specific embodiments and exemplary examples. The above description is illustrative, not exhaustive, and is not limited to the disclosed embodiments; the above description cannot be understood as a limitation of the present invention. The technical solutions between the various embodiments can be combined with each other, but must be based on the ability of ordinary technicians in this field to implement. When the combination of technical solutions is mutually contradictory or cannot be implemented, it should be considered that such a combination of technical solutions does not exist and is not within the scope of protection required by this application. Although the embodiments of the present application have been shown and described, these embodiments can be subjected to various changes, modifications, substitutions and variations without departing from the principles and purposes of the present application. Ordinary technicians in this field can understand that various other specific changes and combinations of embodiments that do not depart from the essence of the present application are made according to the technical inspirations disclosed in this application, and are still within the scope of protection defined by the claims of the present invention and its equivalent technical solutions.
Claims
1. A method for testing heat transfer performance of a heat pipe, characterized in that: A heat pipe used in a nuclear power system, one end of which is heated by an induction coil and the other end exchanges heat with a cold source, is tested for heat transfer performance by: Combining neutron dynamics with thermal power feedback mechanisms, a differential equation for the time-varying fission power of the reactor is established; Establish a differential equation for the time-varying concentration of delayed neutron precursor nuclei; An equation for the total reactivity is established based on the initial reactivity, the reactivity introduced by external control, and the temperature feedback effect; According to the heat transfer model of the simulated nuclear power system, the relationship between the heat flux to be loaded into the heat pipe and the reactor fission power and heat pipe temperature is established; The above equations and relationships are combined to establish a heat source simulation model, and the measured temperature of the heat pipe is substituted into the model to obtain the heat flow that should be loaded into the heat pipe.
2. The heat pipe heat transfer performance testing method according to claim 1, characterized in that: The differential equation for the change of reactor fission power with time is: Among them, Q fiss is the reactor fission power; ρ is the total reactivity; β is the total fraction of delayed neutrons, β i is the delayed neutron fraction of group i; Λ is the neutron generation time; λ i is the decay constant of the delayed neutron precursor nucleus of group i; C i is the concentration of the i-th group of delayed neutron precursor nuclei; S0 is the neutron source; N is the total number of delayed neutron precursor nuclei; i is the group number of the delayed neutron precursor nuclei.
3. The heat pipe heat transfer performance testing method according to claim 1, characterized in that: The differential equation for the delayed neutron precursor concentration changing with time is: Among them, C i is the concentration of delayed neutron precursor nuclei in group i; β i is the delayed neutron fraction of group i; Λ is the neutron generation time; Q fiss is the reactor fission power; i is the decay constant of the delayed neutron precursor nucleus of group i.
4. The heat pipe heat transfer performance testing method according to claim 1, characterized in that: The equation for the overall reactivity is: p=p0+p ext +a Fuel (T Fuel -T0)+a HP (T HP -T0)+a other (T other -T0) Where ρ is the total reactivity; ρ0 is the initial reactivity, representing the intrinsic reactivity of the core at the reference temperature; ρ ext is the external control reactivity; α Fuel is the fuel reactivity temperature coefficient; α HP is the heat pipe reactivity temperature coefficient; α other is the reactivity temperature coefficient of other reactor components; T Fuel is the calculated value of nuclear fuel temperature, T other is the calculated temperature of other reactor components; T HP is the measured temperature of the heat pipe; T0 is the reference temperature.
5. The heat transfer performance testing method of a heat pipe according to claim 4, characterized in that: Calculated value of nuclear fuel temperature T Fuel , calculated temperature values of other reactor components T other Determined by the heat transfer model of the nuclear power system being simulated.
6. The heat pipe heat transfer performance testing method according to claim 1, characterized in that: It also includes the conversion calculation of the induced heat of the heat pipe and the current in the coil. Through the multi-physics simulation calculation results, a conversion model of the current in the induction coil and the heat pipe temperature is established.
7. The heat transfer performance testing method of a heat pipe according to claim 6, characterized in that: Introducing the temperature correction for the heating heat flow, the conversion model is: Q HP-ref =AI 2 +BI+C K=EI 2 +FI+G Q HP =Q HP-ref +K(T HP -T HP-ref ) Where I is the current in the induction coil; T HP-ref is the temperature of the heat pipe under reference operating conditions; Q HP-ref The heat pipe temperature is T HP-ref , the induced heat flux input to the heat pipe when the induction coil is loaded with a current of I; K is the temperature correction coefficient of the heating heat flux; Q HP is the heat flux to be loaded into the heat pipe; A, B, C, E, F, and G are coefficients, which are determined by multi-physics simulation results or calibration test fitting.
8. The heat pipe heat transfer performance testing method according to claim 1, characterized in that: The method also includes calculating the heat flow transmitted by the heat pipe at the cold source, and establishing a heat transfer formula for calculation based on the mass flow rate of the working fluid in the cold source and the temperature at the inlet and outlet of the cold source.
9. An electronic device comprising a memory, a processor, and a computer program stored in the memory and executable in the processor, wherein: When the computer program is executed, the steps corresponding to the heat pipe heat transfer performance testing method according to any one of claims 1 to 8 are performed.
10. A testing system, characterized in that: The heat pipe heat transfer performance testing method according to any one of claims 1 to 8 is adopted, wherein the testing system comprises: The heat pipe is divided into a heating section, a middle section and a heat exchange section along the length direction, and the middle section is coated with a heat insulating material; an induction coil, arranged in the heating section of the heat pipe, for heating the heating section of the heat pipe; an alternating current source, connected to the induction coil to form a loop, for regulating the current I; Heat pipe temperature measurement module, used to measure the actual temperature T of the heating section HP , so that the heat source simulation model obtains the input value; At least two working fluid temperature measurement modules are respectively placed at the inlet and outlet of the cold source, and are used to measure the inlet temperature t of the cold source. i , outlet temperature t o ; Wherein, a pipe is connected between the inlet and outlet of the cold source; a flow measurement module, a valve and a refrigeration device are provided on the pipe; An electronic device is used to collect data from the heat pipe temperature measurement module, the alternating current source, the working fluid temperature measurement module, and the flow measurement module, so as to calculate the heating heat flow of the heat pipe and the current of the induction coil based on the data and the heat source simulation model.