Method and device for measuring calculus value of control rod of nuclear reactor

Abstract

The invention relates to a nuclear reactor control rod calculus value measuring method and device. The method comprises the following steps: when a nuclear reactor is in a preset state, controlling a control rod of the nuclear reactor to move based on a preset rod position, and acquiring a neutron data sequence of the nuclear reactor for each section of rod position of the control rod, and determining a control rod differential value corresponding to each section of rod position of the control rod according to the neutron data sequence, multiplying the control rod differential value corresponding to each rod position by a step number, and summing to obtain a control rod integral value of the control rod. By adopting the method, the universality of the measurement method for the control rod calculus value can be improved.

Description

Technical Field

[0001] This application relates to the field of nuclear energy technology, and in particular to a method and apparatus for measuring the calculus value of control rods in a nuclear reactor. Background Technology

[0002] With the continuous development of energy technology and the increasing demand for electricity, power generation technology is also constantly developing. Among the current power generation technologies, nuclear power generation is gradually being valued by the industry due to its advantages such as low carbon emissions, high energy density, stable and reliable power generation, abundant fuel resources, and low operating costs. As nuclear power generation technology continues to develop, how to safely and reliably control nuclear power generation is the primary concern.

[0003] Currently, the integral value of control rods in nuclear reactors is mainly used to verify the consistency between the actual reactor core and the design. In existing technologies, the dilution / boration method is usually used to measure the integral value of control rods. However, this method has limitations and is not applicable to reactor cores without soluble boron or cores cooled by liquid metal. Summary of the Invention

[0004] Therefore, it is necessary to provide a method, apparatus, computer equipment, computer-readable storage medium, and computer program product for measuring the calculus value of control rods in nuclear reactors that has wider applicability to the above-mentioned technical problems.

[0005] In a first aspect, this application provides a method for measuring the differential value of control rods in a nuclear reactor, comprising: when the nuclear reactor is in a preset state, controlling the control rods of the nuclear reactor to move based on preset rod positions; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold; for each rod position of the control rod, acquiring the neutron data sequence of the nuclear reactor, and determining the differential value of the control rod corresponding to each rod position based on the neutron data sequence; multiplying the differential value of the control rod corresponding to each rod position by the number of steps and summing them to obtain the integral value of the control rod; the differential value and the integral value of the control rod are used for reactivity control and to ensure the reactor's shutdown margin.

[0006] In one embodiment, obtaining a neutron data sequence of a nuclear reactor includes: obtaining multiple neutron flux densities of the nuclear reactor within a target time period; determining multiple reactivity values ​​of the nuclear reactor within the target time period based on each neutron flux density and the target time period; and determining a neutron data sequence based on each reactivity value and the target time period.

[0007] In one embodiment, the neutron data sequence includes first neutron data during the movement of the control rods and second neutron data during the process of the nuclear reactor returning to the preset state. Determining the differential value of the control rod corresponding to each segment of the control rod based on the neutron data sequence includes: querying the first reactivity value corresponding to the initial moment in the first neutron data and determining the second reactivity value based on the second neutron data; and determining the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0008] In one embodiment, the reactivity value of the nuclear reactor is adjusted to a reactivity threshold by controlling the control rods to be fully extended and continuously reducing the reactor loop temperature at a preset rate until the reactivity value reaches the reactivity threshold; wherein, controlling the movement of the control rods based on preset positions includes: continuously reducing the reactor loop temperature at a preset rate and controlling the control rods to be inserted based on preset positions.

[0009] In one embodiment, the reactivity value of the nuclear reactor is adjusted to a reactivity threshold by controlling the control rods to be fully extended and reducing the loop temperature of the nuclear reactor until the reactivity value reaches the reactivity threshold; wherein, controlling the movement of the control rods of the nuclear reactor based on preset rod positions includes: controlling the control rods to be inserted based on preset rod positions, and reducing the loop temperature until the reactivity value reaches the reactivity threshold after the rate of change of the reactivity value is less than the rate of change threshold.

[0010] In one embodiment, the method further includes: determining the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod; and sending the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to a display device.

[0011] In one embodiment, the method further includes: generating a fitting curve of the reactivity value and time of the nuclear reactor based on the neutron data sequence of each segment of the control rod; and sending the fitting curve, the differential value of each control rod, and the integral value of the control rod to a display device.

[0012] In one embodiment, the preset state further includes: the number of neutrons generated and the number of neutrons consumed in the nuclear reactor are the same, and / or, the core temperature of the nuclear reactor reaches a temperature threshold.

[0013] In one embodiment, the method is applied to the control rod control equipment of a nuclear reactor, which includes a boron-free thermal neutron reactor in coolant.

[0014] Secondly, this application also provides a device for measuring the differential value of control rods in a nuclear reactor, comprising: a control rod control module, used to control the movement of control rods in the nuclear reactor based on preset rod positions when the nuclear reactor is in a preset state; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold; a control rod differential value acquisition module, used to acquire the neutron data sequence of the nuclear reactor for each rod position, and determine the control rod differential value corresponding to each rod position based on the neutron data sequence; and a control rod integral value acquisition module, used to multiply the control rod differential value corresponding to each rod position by the number of steps and then sum them to obtain the control rod integral value of the control rod; the control rod differential value and the control rod integral value are used for reactivity control and to ensure the reactor's shutdown margin.

[0015] Thirdly, this application also provides a computer device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the method described in the first aspect.

[0016] Fourthly, this application also provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the method described in the first aspect.

[0017] Fifthly, this application also provides a computer program product, including a computer program that, when executed by a processor, implements the steps of the method described in the first aspect.

[0018] The aforementioned method, apparatus, computer equipment, computer-readable storage medium, and computer program product for measuring the integral value of control rods in nuclear reactors, under the condition that the nuclear reactor is in a preset state (the preset state may be that the reactivity value of the nuclear reactor has reached a reactivity threshold), control rods of the nuclear reactor are moved based on preset rod positions. The integral value of the control rods is determined simply and with high precision through segmented rod position movement. For each segment of the control rod, the neutron data sequence of the nuclear reactor is acquired, and the differential value of the control rod corresponding to each segment of the control rod is determined based on the neutron data sequence. After the differential value of the control rod corresponding to each segment of the control rod is measured, the differential values ​​of each control rod are summed to obtain the integral value of the control rod. The integral value of the control rod is used to determine the operating strategy of the nuclear reactor. This method enables the measurement of the integral value of control rods of control rods of various types of nuclear reactors, improving the applicability of the measurement of the integral value of control rods. Attached Figure Description

[0019] To more clearly illustrate the technical solutions in the embodiments of this application or related technologies, the drawings used in the description of the embodiments of this application or related technologies will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other related drawings can be obtained based on these drawings without creative effort.

[0020] Figure 1 This is a diagram illustrating the application environment of a method for measuring the calculus value of control rods in a nuclear reactor, as described in one embodiment.

[0021] Figure 2 This is a flowchart illustrating a method for measuring the calculus value of control rods in a nuclear reactor, as described in one embodiment.

[0022] Figure 3 This is a flowchart illustrating the steps for obtaining a neutron data sequence in one embodiment;

[0023] Figure 4 This is a flowchart illustrating the steps for determining the differential value of a control rod in one embodiment.

[0024] Figure 5 This is a flowchart illustrating the steps for adjusting the reactivity values ​​of a nuclear reactor in one embodiment.

[0025] Figure 6 This is a flowchart illustrating the steps of moving control rods in a nuclear reactor in one embodiment.

[0026] Figure 7 This is a flowchart illustrating the reactivity adjustment steps for a nuclear reactor in another embodiment;

[0027] Figure 8 This is a flowchart illustrating the steps of moving control rods in a nuclear reactor, as described in another embodiment.

[0028] Figure 9 This is a flowchart illustrating the steps of sending data to a display device in one embodiment;

[0029] Figure 10 This is a flowchart illustrating the step of sending data to a display device in another embodiment;

[0030] Figure 11 This is a schematic diagram of the fitting curve of the isothermal temperature coefficient in one embodiment;

[0031] Figure 12 This is a flowchart illustrating a method for measuring the calculus value of control rods in a nuclear reactor, as described in another embodiment.

[0032] Figure 13This is a structural block diagram of a control rod calculus value measurement device for a nuclear reactor in one embodiment.

[0033] Figure 14 This is an internal structural diagram of a computer device in one embodiment. Detailed Implementation

[0034] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0035] It should be noted that the terms "first," "second," etc., used in this application can be used to describe various elements, but these elements are not limited by these terms. These terms are only used to distinguish the first element from the second element. The terms "comprising" and "having," and any variations thereof, used in this application, are intended to cover non-exclusive inclusion. The term "multiple" used in this application refers to two or more. The term "and / or" used in this application refers to one of the embodiments, or any combination of multiple embodiments.

[0036] The method for measuring the integral value of control rods in nuclear reactors provided in this application can be applied to, for example... Figure 1 The application environment shown includes at least a nuclear reactor 101, control rods 101-1, and control equipment 102 for the control rods.

[0037] Nuclear reactor 101 includes a thermal neutron reactor used to generate high temperatures through a controlled chain fission reaction. Nuclear reactor 101 includes control rods 101-1. Nuclear reactor 101 may include a boron-free thermal neutron reactor in the coolant. Nuclear reactor 101 may also include a research reactor, liquid metal reactor, pressurized water reactor, boiling water reactor, heavy water reactor, graphite gas-cooled reactor, fast neutron reactor, molten salt reactor, etc.

[0038] Control rod 101-1 is used to regulate or terminate a controlled chain fission reaction in a nuclear reactor by absorbing neutrons. Control rods are typically made of materials with a high neutron absorption cross-section, such as silver-indium-cadmium alloys, boron carbide, gadolinium, hafnium, etc.

[0039] The control device 102 for the control rods is used to monitor the state of the nuclear reactor. When the nuclear reactor is detected to be in a preset state, the control rod 101-1 is moved according to a preset rod position. For each rod position, the neutron data sequence of the nuclear reactor 101 is acquired. The differential value of the control rod for each rod position is determined based on the neutron data sequence. The differential value of the control rod for each rod position is multiplied by the number of steps and then summed to obtain the integral value of the control rod 101-1. The control device 102 can be a server connected to multiple monitoring units and / or control units. This server can be a standalone physical server, a server cluster or distributed system composed of multiple physical servers, or a cloud server providing cloud computing services. The control device 102 can acquire data from the nuclear reactor 101 through a monitoring network; the monitoring network can be constructed using multiple different types of monitoring sensors.

[0040] In practical scenarios, the control rod integral value measurement test is one of the most important tests during reactor commissioning. For large pressurized water reactor units, the control rod integral value is usually measured through the dilution / boration method. However, the dilution / boration method requires boron in the reactor coolant, so it cannot be used for reactor cores without soluble boron, such as some research reactors and advanced liquid metal reactors. In these reactor types, the integral value of the control rod is usually achieved by alternately inserting and removing two or more control rods. During the measurement process, there is an interference effect between the two or more control rods, which is not conducive to the verification of theoretical calculation results or nuclear design procedures.

[0041] During reactor startup, the temperature typically varies over a wide range. Traditional methods for measuring the integral value of control rods, such as the dilution / boration method, have limitations when there is no boron in the coolant. The method of alternating insertion and removal of control rods to measure the integral value of control rods is also problematic due to interference effects between control rods, making the measurement results unsuitable for verifying theoretical calculations or nuclear design procedures.

[0042] To address this, during temperature changes, the reactivity of the reactor core changes due to variations in coolant density and the Doppler effect of the fuel. This reactivity coefficient is called the isothermal temperature coefficient. For thermal neutron reactors with boron-free coolant, this reactivity coefficient is larger, and reactivity can be increased or decreased by adjusting the temperature of the primary loop. Therefore, if it is used as a means to compensate for core reactivity after control rod insertion or removal, the value of each segment of the control rod can be measured, thereby enabling the measurement of the calculus value of the control rod.

[0043] This application introduces reactivity by adjusting the primary loop temperature to counteract the reactivity introduced by the control rod action, thereby enabling the measurement of the control rod calculus value. On the one hand, the reactivity introduction method and speed are more uniform and controllable; on the other hand, the isothermal temperature coefficient of the reactor core can be measured simultaneously, increasing the isothermal temperature coefficient measurement function.

[0044] In one exemplary embodiment, such as Figure 2 As shown, a method for measuring the calculus value of control rods in a nuclear reactor is provided, which can be applied to... Figure 1 The following steps are used as an example of the control device of the control rod in the process of illustration, including steps 201 to 203.

[0045] Step 201: When the nuclear reactor is in a preset state, the control rods controlling the nuclear reactor are moved based on preset rod positions.

[0046] During implementation, the control equipment monitors the reactor core status. If the core status is detected to be in a preset state, the control rods of the reactor are moved based on preset positions to measure the control rod calculus value in a segmented manner. Here, the control rod movement can be either insertion or removal; optionally, the control rod movement based on preset positions can include either removal or insertion.

[0047] In this application, the preset state refers to the initial state of the reactor core. The preset state facilitates the measurement of the calculus value of the control plate. Specifically, the preset state includes the reactor's reactivity value reaching a reactivity threshold. Furthermore, the preset state may also include the reactor's neutron generation and consumption being equal; this state can also represent the reactor being in a critical state. Alternatively, the preset state may include the test rod being fully extracted or almost fully extracted. If it is almost fully extracted, the end value of the unextracted portion needs to be measured, such as by a periodic method or an inverse dynamic method. Alternatively, the preset state may include the core temperature being at the upper limit of a proven permissible range, i.e., the reactor core temperature reaching a temperature threshold. Optionally, the nuclear reactor includes a boron-free thermal neutron reactor in the coolant.

[0048] It should be noted that the preset state may include any one of the above states, or any combination of two or more of the above states, which will not be elaborated here.

[0049] During the movement of the control rod, it can be moved based on a preset rod position. The control rod can be divided into multiple segments, and each segment can be inserted or removed. For each segment, the differential value of the control rod corresponding to that segment can be determined. After the measurement of each segment is completed, the integral value of the control rod corresponding to the control rod is obtained. Furthermore, each segment can be divided into multiple steps, and the movement can be based on a preset number of steps to obtain the differential value of the control rod for each step.

[0050] Step 202: For each segment of the control rod, obtain the neutron data sequence of the nuclear reactor, and determine the differential value of the control rod corresponding to each segment of the control rod based on the neutron data sequence.

[0051] During implementation, for each segment of the control rod, the control equipment detects the neutron signal in the nuclear reactor, constructs a neutron data sequence based on the neutron signal, and determines the differential value of the control rod corresponding to each segment based on the neutron data sequence and the corresponding time. This process of moving the rod and calculating the differential value of the control rod is repeated until the measurement is complete, resulting in multiple differential values ​​of the control rod corresponding to multiple rod segments. The measurement of the differential values ​​of the control rods for other rod segments can be performed with reference to the above method and will not be elaborated here. Here, each segment of the rod can correspond to one step. When each segment of the rod has one step, the differential value of each step can be used as the differential value of that rod segment. When each segment of the rod includes multiple steps, the value corresponding to that rod segment can be determined using the above method, and the differential value of the control rod is obtained by dividing this value by the number of steps.

[0052] In this application, the differential value of the control rod is a parameter in nuclear reactor physics used to describe the amount of reactivity change caused by the control rod moving a small distance at a specific position. For example, the amount of reactivity introduced (or removed) by the control rod moving a unit distance at its current position. The differential value of the control rod can provide a reference for operators to carry out reactivity control.

[0053] The neutron data sequence includes the reactivity values ​​of the nuclear reactor at various times. For each segment of the control rod, the sampling time corresponding to the neutron data sequence may include: the time corresponding to the control rod movement process, and the time corresponding to the nuclear reactor returning to the preset state, that is: the time corresponding to the reactivity value of the nuclear reactor reaching the reactivity threshold. Accordingly, the neutron data sequence may include the first neutron data during the control rod movement process, and the second neutron data during the nuclear reactor returning to the preset state.

[0054] During execution, the control equipment can also be connected to external detectors and instruments. The control equipment can receive current signals sent by the external detectors and instruments, calculate the reactivity values ​​of the nuclear reactor based on the current signals, and construct a neutron data sequence based on the reactivity values.

[0055] Furthermore, the control device can also acquire temperature data during the movement of the control rod, construct a temperature change curve based on the temperature data, and determine the isothermal temperature coefficient based on the temperature change curve and the neutron data sequence.

[0056] The preset rod position can be the rod position corresponding to each step of the control rod, or the preset rod position can be a rod position formed by a combination of multiple steps. In the case of multiple steps, the differential value of the control rod corresponding to the rod position can be determined by the neutron data sequence and the number of steps corresponding to the rod position.

[0057] Step 203: Multiply the differential value of the control rod corresponding to each rod position by the number of steps and sum them to obtain the integral value of the control rod.

[0058] During implementation, after obtaining the differential values ​​of multiple control rods, the differential values ​​of each step corresponding to each segment can be added together to obtain a summation result, and the summation result is determined as the control rod integral value of the control rod; or, the differential value of each segment can be multiplied by the number of steps corresponding to each segment and added together to obtain a summation result, and the summation result is determined as the control rod integral value of the control rod.

[0059] During execution, the reactivity corresponding to each segment of the test rod is accumulated to obtain the accumulated result. This accumulated value is the integral value of the control rod (if the initial state of the control rod is not fully extracted, this end value also needs to be added to the integral value).

[0060] In this application, the integral value of control rods is a fundamental parameter in nuclear reactor physics, used to describe the total change in reactivity introduced when a control rod is inserted from a reference position (usually in a fully withdrawn state) to a specified depth. For example, it could be the cumulative total change in reactivity introduced when inserted from a fully withdrawn state to a certain depth, or the cumulative total change in reactivity removed when withdrawn from a fully inserted state to a certain depth. The integral value of control rods is used to determine the reactivity control of a nuclear reactor and to ensure the reactor's shutdown margin. It should be noted that the method for measuring the integral value of control rods in this application can be applied to control rod control equipment in nuclear reactors. It should also be noted that the integral value of control rods in this application refers to both the differential value and the integral value of the control rods.

[0061] In the aforementioned method for measuring the integral value of control rods in a nuclear reactor, under the condition that the nuclear reactor is in a preset state (which may be that the reactivity value of the nuclear reactor has reached a reactivity threshold), the control rods of the nuclear reactor are moved based on preset rod positions. The integral value of the control rods is determined simply and with high precision through segmented rod position movement. For each segment of the control rod, the neutron data sequence of the nuclear reactor is acquired, and the integral value of the control rod corresponding to each segment of the control rod is determined based on the neutron data sequence. This process continues until the integral value of the control rod corresponding to each segment of the control rod is measured. Finally, the reactivity of each segment of the control rod is summed to obtain the integral value of the control rod. The integral value of the control rod is used to guide the reactivity control of the nuclear reactor and to ensure the reactor's shutdown margin. This application realizes the measurement of the integral value of control rods for various types of nuclear reactors, improving the versatility of the measurement of the integral value of control rods.

[0062] Based on the above exemplary embodiment, the following provides a method for measuring the calculus value of control rods in a nuclear reactor in one or more exemplary embodiments, which is applied to... Figure 1 The following explanation will be based on the control equipment in the example.

[0063] In practical scenarios, the calculus value of the control rod can be determined through reactivity, and a neutron data sequence can be constructed based on the reactivity data determined at each time point; in one optional implementation provided in this application, such as Figure 3 As shown, obtaining the neutron data sequence includes steps 301 to 303:

[0064] Step 301: Obtain multiple neutron flux densities of the nuclear reactor within the target time period.

[0065] During implementation, the control equipment obtains the neutron flux density level of the nuclear reactor at each sampling time within the target time period through an external detector, thus obtaining multiple neutron flux density values.

[0066] Step 302: Determine multiple reactivity values ​​of the nuclear reactor within the target time period based on the neutron flux density levels and the target time period.

[0067] During implementation, for each sampling moment, the control equipment solves the inverse dynamic equation based on the neutron flux density to obtain the reactivity of the reactor core, until the calculation is completed for each sampling moment, resulting in multiple reactivity values.

[0068] Step 303: Determine the neutron data sequence based on the reactivity values ​​and the target time period.

[0069] During implementation, the control equipment sorts multiple reactivity values ​​according to the sampling time to obtain sorted reactivity values. Based on the sorted reactivity data and the sampling time, a neutron data sequence is constructed.

[0070] One optional implementation provided in this application accurately determines the reactivity at each sampling moment by calculating the reactivity value at each sampling moment, thereby constructing a neutron data sequence, improving the reliability of the neutron data sequence, and further improving the accuracy of the control rod calculus value.

[0071] In the process of determining the differential value, the differential value of the control rod can be obtained by subtracting the reactive value at the initial time from the reactive value at the final time; in one optional implementation provided by this application, such as Figure 4 As shown, determining the differential value of the control rod includes steps 401 to 402:

[0072] Step 401: Query the first reactivity value corresponding to the initial time in the first neutron data, and determine the second reactivity value based on the second neutron data.

[0073] In this application, the first neutron data represents the reactivity value during the movement of the control rods, and the second neutron data represents the reactivity value during the process of the nuclear reactor returning to a preset state after the control rods stop moving. During implementation, the control equipment can query the first reactivity value corresponding to the initial moment in the first neutron data and determine the second reactivity value based on the second neutron data.

[0074] In determining the second reactivity value, there are two scenarios: First, when the temperature of the nuclear reactor changes at a uniform and continuous rate, a linear straight line can be fitted based on the second neutron data to show the reactivity value changing over time. The reactivity value corresponding to the intersection of the time corresponding to the first reactivity value and this straight line can be determined as the second reactivity value. Second, when the temperature of the nuclear reactor changes non-uniformly but remains constant, the value after the rate of change of the nuclear reactor's reactivity value has stabilized can be used as the second reactivity value. After obtaining the second reactivity value, the temperature of the nuclear reactor can be adjusted until the nuclear reactor is in a preset state.

[0075] Step 402: Determine the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0076] During implementation, the control device subtracts the first reactivity value from the second reactivity value to obtain the reactivity difference, which is then used as the differential value of the control rod.

[0077] It should be noted that the method for determining the differential value of the control rod provided in this embodiment can be applied to the case where the number of control rod steps is 1. When the number of control rod steps is n, the differential value of the control rod can be obtained by multiplying the reactivity difference by the number of steps n.

[0078] One optional implementation method provided in this application determines the differential value of the control rod by determining the reactivity difference, which is simple, fast, and saves computing power, while also ensuring the accuracy of the differential value of the control rod.

[0079] In practical scenarios, it is also necessary to maintain the nuclear reactor in its initial state beforehand, which can maintain the reactivity value of the nuclear reactor at the reactivity threshold; in one optional implementation provided in this application, such as Figure 5 As shown, the reactivity values ​​of the nuclear reactor are adjusted through step 501:

[0080] Step 501: The control rod is in the fully extended state, and the loop temperature of the nuclear reactor is continuously reduced according to a preset rate until the reactivity value reaches the reactivity threshold.

[0081] During implementation, the control equipment first controls the control rods in the nuclear reactor to be fully extended, and then continuously and uniformly reduces the primary circuit temperature of the nuclear reactor according to a preset rate. At the same time, the reactivity of the reactor core is measured until the reactor core is in a slightly supercritical state; optionally, the reactivity threshold is 50 pcm.

[0082] In addition, the control rods can be controlled to be fully inserted into the reactor core and the loop temperature of the nuclear reactor can be continuously increased at a preset rate until the reactivity value reaches the reactivity threshold; at this time, the reactivity threshold can be -50 pcm.

[0083] During execution, the control equipment can establish a stable primary cooling rate by adjusting the valve opening, etc.; optionally, the preset state also includes: the core neutron flux level is close to the upper limit of the zero-power physics test range.

[0084] Furthermore, as the circuit temperature is continuously reduced until the reactivity reaches a threshold, a control rod can be moved to counteract the increase in reactivity caused by the temperature reduction, while simultaneously measuring the reactivity introduced by the inserted control rod; in one optional embodiment provided by this application, such as Figure 6 As shown, the control rods of the nuclear reactor are moved, including step 601:

[0085] Step 601: Continuously reduce the loop temperature of the nuclear reactor according to a preset rate, and control the control rods to be inserted based on preset rod positions.

[0086] During implementation, the control equipment continuously reduces the loop temperature of the nuclear reactor according to a preset rate, while the control rods of the nuclear reactor are inserted based on preset positions.

[0087] In addition, the loop temperature of the nuclear reactor can be continuously increased according to a preset rate, and the control rods can be raised based on preset rod positions.

[0088] In one optional implementation provided by this application, the loop temperature is continuously reduced, and reactivity is continuously and stably introduced, avoiding the influence of other reactivity introduction methods (such as proposing other control rods) on the calculus value of the target control rod, thereby improving the accuracy and reliability of the calculus value of the control rod.

[0089] In addition, after each control rod segment is moved, the temperature can be directly reduced to near the reactivity threshold, and the next control rod movement can be performed only after the nuclear reactor's reactivity has stabilized; in one optional embodiment provided in this application, such as Figure 7 As shown, the reactivity values ​​of the nuclear reactor are adjusted through step 701:

[0090] Step 701: The control rods are fully withdrawn, and the loop temperature of the nuclear reactor is reduced until the reactivity value reaches the reactivity threshold.

[0091] During implementation, the control equipment keeps the control rods of the nuclear reactor fully extended and lowers the reactor loop temperature until the reactivity value detected by the control equipment reaches the reactivity threshold. In addition to the above embodiments, rapid cooling can also be achieved using coolant from other loops during the cooling process.

[0092] In addition, the control rods can be controlled to be fully inserted into the reactor core, and the loop temperature of the nuclear reactor can be increased until the reactivity value reaches the reactivity threshold.

[0093] Furthermore, after the control rods of the nuclear reactor are moved to the preset position, the control equipment can, once the measured reactivity values ​​have stabilized, further reduce the loop temperature to bring the nuclear reactor to the preset state; in one optional embodiment provided in this application, such as Figure 8 As shown, the control rods of the nuclear reactor are moved, including step 801:

[0094] Step 801: The control rod is inserted based on the preset rod position, and after the rate of change of the reactivity value is less than the rate of change threshold, the circuit temperature is reduced until the reactivity value reaches the reactivity threshold.

[0095] During implementation, the control equipment inserts control rods based on preset positions and simultaneously monitors the rate of change of the nuclear reactor's reactivity values. Once the reactivity values ​​stabilize, i.e., the rate of change is less than a threshold, the loop temperature continues to decrease until the reactivity values ​​reach the threshold. Alternatively, once the rate of change of the reactivity values ​​is less than the threshold, the nuclear reactor's state can be maintained at a preset state.

[0096] In addition, the control rod can be raised based on a preset rod position, and the circuit temperature can be increased until the reactivity value reaches the reactivity threshold after the rate of change of the reactivity value is less than the rate of change threshold.

[0097] One optional implementation method provided in this application is to directly reduce the temperature instead of continuously cooling at a constant rate, which is more convenient and improves the measurement efficiency of the calculus value of the control rod.

[0098] In practical scenarios, the calculus value of the control rods of the nuclear reactor can also be sent to a display device for display to the user. Furthermore, the control device can calculate the isothermal temperature coefficient and send it to the display device. In one optional embodiment provided in this application, such as... Figure 9 As shown, the method further includes steps 901 to 902:

[0099] Step 901: Determine the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod.

[0100] During implementation, the control equipment reads the reactivity and core temperature at each sampling moment in the neutron data sequence corresponding to each segment of the control rod. Based on each reactivity, it determines the fitting slope of the reactivity relative to the core temperature, and determines the fitting slope as the isothermal temperature coefficient of the nuclear reactor.

[0101] Step 902: Send the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to the display device.

[0102] During implementation, the control equipment acquires the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod, and sends these values ​​to the display device.

[0103] In addition, the isothermal temperature coefficient can also be calculated by the user. For this purpose, a fitting curve can be constructed based on the neutron data sequence and sent to a display device, allowing the user to view the isothermal temperature coefficient determined based on the fitting curve on the display device. In one optional implementation provided by this application, such as... Figure 10 As shown, the control rods of the nuclear reactor are moved, including steps 1001 to 1002:

[0104] Step 1001: Based on the neutron data sequence of each segment of the control rod, generate a fitting curve of the nuclear reactor's reactivity values ​​and time.

[0105] During implementation, the control equipment plots a scatter plot based on the reactivity values ​​corresponding to each sampling time in the neutron data sequence, and obtains a fitting curve of the reactivity values ​​and time of the nuclear reactor based on the scatter plot.

[0106] For example, such as Figure 11 The figure shown is a fitted curve of the reactivity value and time of the nuclear reactor.

[0107] Step 1002: Send the fitted curve, the differential value of each control bar, and the integral value of the control bar to the display device.

[0108] During implementation, the control device acquires the fitted curve, the differential value of each control bar, and the integral value of the control bar, and sends the fitted curve, the differential value of each control bar, and the integral value of the control bar to the display device.

[0109] One optional implementation provided in this application is to send the generated data to a display device, so that the user can view the calculated data on the display device, thereby improving the user's perception and enabling the user to determine the consistency between the nuclear reactor and the design based on the data.

[0110] In one embodiment, see Figure 12 The document illustrates a flowchart of a method for measuring the integral value of control rods in a nuclear reactor, provided in an embodiment of this application. This method can be applied to... Figure 1 In the control device shown. For example... Figure 12 As shown, the method for measuring the calculus value of the control rods in this nuclear reactor may include the following steps:

[0111] Step 1201: The loop temperature of the nuclear reactor is reduced uniformly at a preset rate until the nuclear reactor reaches its initial state.

[0112] Step 1202: Continuously and uniformly reduce the loop temperature of the nuclear reactor, and for each preset position of the control rod, control the nuclear reactor control rods to be inserted according to the preset number of steps.

[0113] Step 1203: Obtain multiple neutron flux densities of the nuclear reactor within the target time period.

[0114] Step 1204: Determine multiple reactivity values ​​of the nuclear reactor within the target time period based on the neutron flux density and the target time period.

[0115] Step 1205: Determine the neutron data sequence based on the reactivity values ​​and the target time period.

[0116] Step 1206: Query the first reactivity value corresponding to the initial time in the first neutron data, and determine the second reactivity value based on the second neutron data.

[0117] Step 1207: Determine the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0118] Step 1208: Sum the segment values ​​of the control rods corresponding to each rod position to obtain the integral value of the control rod.

[0119] It should be noted that any one or more of steps 1201 to 1208 can be combined to form a new implementation method according to the needs of implementation and deployment. Furthermore, any one or more technical features in the technical solution composed of steps 1201 to 1208 can also be combined to form a new implementation method according to the actual deployment needs, or technical features in one or more optional implementations provided by one or more of the above embodiments can be combined to form a new implementation method. These will not be elaborated on here.

[0120] It should be understood that although the steps in the flowcharts of the embodiments described above are shown sequentially according to the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless explicitly stated herein, there is no strict order restriction on the execution of these steps, and they can be executed in other orders. Moreover, at least some steps in the flowcharts of the embodiments described above may include multiple steps or multiple stages. These steps or stages are not necessarily completed at the same time, but can be executed at different times. The execution order of these steps or stages is not necessarily sequential, but can be performed alternately or in turn with other steps or at least some of the steps or stages in other steps. It is understood that the steps in different embodiments can be freely combined as needed, and all non-contradictory solutions formed by such combinations are within the scope of protection of this application.

[0121] Based on the same inventive concept, this application also provides a device for measuring the integral value of control rods in a nuclear reactor to implement the aforementioned method for measuring the integral value of control rods in a nuclear reactor. The solution provided by this device is similar to the solution described in the above method. Therefore, the specific limitations of the one or more embodiments of the device for measuring the integral value of control rods in a nuclear reactor provided below can be found in the limitations of the method for measuring the integral value of control rods in a nuclear reactor described above, and will not be repeated here.

[0122] In one exemplary embodiment, such as Figure 13 As shown, a device for measuring the differential value of control rods in a nuclear reactor is provided, comprising: a control rod control module 1301, a control rod differential value acquisition module 1302, and a control rod integral value acquisition module 1303. The control rod control module 1301 is used to control the movement of the control rods of the nuclear reactor based on preset rod positions when the nuclear reactor is in a preset state; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold. The control rod differential value acquisition module 1302 is used to acquire the neutron data sequence of the nuclear reactor for each rod position and determine the control rod differential value corresponding to each rod position based on the neutron data sequence. The control rod integral value acquisition module 1303 is used to sum the control rod values ​​corresponding to each rod position to obtain the control rod integral value of the control rod. The control rod differential value and the control rod integral value are used for reactivity control and to ensure the reactor's shutdown margin.

[0123] In one embodiment, the control rod differential value acquisition module 1302 includes a neutron flux density acquisition unit, a reactivity value determination unit, and a neutron data sequence determination unit, wherein: the neutron flux density acquisition unit is used to acquire multiple neutron flux densities of the nuclear reactor within a target time period; the reactivity value determination unit is used to determine multiple reactivity values ​​of the nuclear reactor within the target time period based on each neutron flux density and the target time period; and the neutron data sequence determination unit is used to determine a neutron data sequence based on each reactivity value and the target time period.

[0124] In one embodiment, the control rod differential value acquisition module 1303 includes a reactivity value determination unit and a differential value determination unit, wherein: the reactivity value determination unit is used to query the first reactivity value corresponding to the initial time in the first neutron data, and determine the second reactivity value according to the second neutron data; the differential value determination unit is used to determine the control rod differential value according to the first reactivity value and the second reactivity value.

[0125] In one embodiment, the control rod control module 1301 includes a first control unit, wherein: the first control unit is used to continuously reduce the loop temperature of the nuclear reactor according to a preset rate, and control the control rod to be inserted based on a preset rod position; wherein the reactivity value of the nuclear reactor is adjusted to the reactivity threshold in the following manner: the control rod is controlled to be in a fully withdrawn state, and the loop temperature of the nuclear reactor is continuously reduced according to a preset rate until the reactivity value reaches the reactivity threshold.

[0126] In one embodiment, the control rod control module 1301 includes a second control unit, wherein: the second control unit is used to control the control rod to be inserted based on a preset rod position, and after the rate of change of the reactivity value is less than a rate of change threshold, to reduce the loop temperature until the reactivity value reaches the reactivity threshold; wherein, the reactivity value of the nuclear reactor is adjusted to the reactivity threshold in the following manner: controlling the control rod to be in a fully withdrawn state, and reducing the loop temperature of the nuclear reactor until the reactivity value reaches the reactivity threshold.

[0127] In one embodiment, the apparatus further includes an isothermal temperature coefficient determination unit and a transmission unit, wherein: the isothermal temperature coefficient determination unit is used to determine the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod; the transmission unit is used to transmit the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to a display device.

[0128] In one embodiment, the apparatus further includes a curve generation unit and a transmission unit, wherein: the curve generation unit is used to generate a fitting curve of the reactivity value and time of the nuclear reactor based on the neutron data sequence of each segment of the control rod; and the transmission unit is used to transmit the fitting curve, the differential value of each control rod, and the integral value of the control rod to a display device.

[0129] Each module in the aforementioned control rod calculus value measurement device for nuclear reactors can be implemented entirely or partially through software, hardware, or a combination thereof. These modules can be embedded in hardware within or independently of the processor in a computer device, or stored in software within the memory of a computer device, so that the processor can invoke and execute the corresponding operations of each module.

[0130] In one exemplary embodiment, a computer device is provided, which may be a server, and its internal structure diagram may be as follows: Figure 14As shown, the computer device includes a processor, memory, input / output (I / O) interfaces, and a communication interface. The processor, memory, and I / O interfaces are connected via a system bus, and the communication interface is also connected to the system bus via the I / O interfaces. The processor provides computational and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system, computer programs, and a database. The internal memory provides the environment for the operation of the operating system and computer programs stored in the non-volatile storage media. The database stores calculus value measurement data for control rods. The I / O interfaces are used for exchanging information between the processor and external devices. The communication interface is used for communication with external terminals via a network connection. When the computer program is executed by the processor, it implements a method for measuring the calculus value of control rods in a nuclear reactor.

[0131] Those skilled in the art will understand that Figure 14 The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the computer device to which the present application is applied. Specific computer devices may include more or fewer components than those shown in the figure, or combine certain components, or have different component arrangements.

[0132] In an exemplary embodiment, a computer device is provided, including a memory and a processor. The memory stores a computer program, and the processor executes the computer program to perform the following steps: when the nuclear reactor is in a preset state, the control rods controlling the nuclear reactor move based on preset rod positions; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold; for each rod position of the control rod, the neutron data sequence of the nuclear reactor is acquired, and the differential value of the control rod corresponding to each rod position is determined based on the neutron data sequence; the differential value of the control rod corresponding to each rod position is multiplied by the number of steps and then summed to obtain the integral value of the control rod; the differential value of the control rod and the integral value of the control rod are used for reactivity control and to ensure the reactor's shutdown margin.

[0133] In one embodiment, when the processor executes the computer program, it further performs the following steps: acquiring multiple neutron flux densities of the nuclear reactor within a target time period; determining multiple reactivity values ​​of the nuclear reactor within the target time period based on each neutron flux density and the target time period; and determining a neutron data sequence based on each reactivity value and the target time period.

[0134] In one embodiment, when the processor executes the computer program, it further performs the following steps: querying the first reactivity value corresponding to the initial time in the first neutron data, and determining the second reactivity value based on the second neutron data; and determining the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0135] In one embodiment, the processor, when executing the computer program, also performs the following steps: controlling the control rods to be in a fully extended state and continuously reducing the loop temperature of the nuclear reactor at a preset rate until the reactivity value reaches the reactivity threshold.

[0136] In one embodiment, the processor, when executing the computer program, also performs the following steps: continuously reducing the loop temperature of the nuclear reactor at a preset rate, and controlling the control rods to be inserted based on preset rod positions.

[0137] In one embodiment, the processor, while executing the computer program, also performs the following steps: controlling the control rods to be in a fully deployed state and reducing the loop temperature of the nuclear reactor until the reactivity value reaches the reactivity threshold.

[0138] In one embodiment, when the processor executes the computer program, it further performs the following steps: controlling the control rod to be inserted based on a preset rod position, and reducing the circuit temperature until the reactivity value reaches the reactivity threshold after the rate of change of the reactivity value is less than the rate of change threshold.

[0139] In one embodiment, when the processor executes the computer program, it also performs the following steps: determining the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod; and sending the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to a display device.

[0140] In one embodiment, when the processor executes the computer program, it also performs the following steps: generating a fitting curve of the reactivity value and time of the nuclear reactor based on the neutron data sequence of each segment of the control rod; and sending the fitting curve, the differential value of each control rod, and the integral value of the control rod to a display device.

[0141] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, it performs the following steps: when the nuclear reactor is in a preset state, the control rods controlling the nuclear reactor move based on preset rod positions; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold; for each rod position of the control rod, the neutron data sequence of the nuclear reactor is acquired, and the differential value of the control rod corresponding to each rod position is determined based on the neutron data sequence; the differential value of the control rod corresponding to each rod position is multiplied by the number of steps and then summed to obtain the integral value of the control rod; the differential value of the control rod and the integral value of the control rod are used for reactivity control and to ensure the reactor's shutdown margin.

[0142] In one embodiment, when the processor executes the computer program, it further performs the following steps: acquiring multiple neutron flux densities of the nuclear reactor within a target time period; determining multiple reactivity values ​​of the nuclear reactor within the target time period based on each neutron flux density and the target time period; and determining a neutron data sequence based on each reactivity value and the target time period.

[0143] In one embodiment, when the processor executes the computer program, it further performs the following steps: querying the first reactivity value corresponding to the initial time in the first neutron data, and determining the second reactivity value based on the second neutron data; and determining the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0144] In one embodiment, the processor, when executing the computer program, also performs the following steps: controlling the control rods to be in a fully extended state and continuously reducing the loop temperature of the nuclear reactor at a preset rate until the reactivity value reaches the reactivity threshold.

[0145] In one embodiment, the processor, when executing the computer program, also performs the following steps: continuously reducing the loop temperature of the nuclear reactor at a preset rate, and controlling the control rods to be inserted based on preset rod positions.

[0146] In one embodiment, the processor, while executing the computer program, also performs the following steps: controlling the control rods to be in a fully deployed state and reducing the loop temperature of the nuclear reactor until the reactivity value reaches the reactivity threshold.

[0147] In one embodiment, when the processor executes the computer program, it further performs the following steps: controlling the control rod to be inserted based on a preset rod position, and reducing the circuit temperature until the reactivity value reaches the reactivity threshold after the rate of change of the reactivity value is less than the rate of change threshold.

[0148] In one embodiment, when the processor executes the computer program, it also performs the following steps: determining the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod; and sending the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to a display device.

[0149] In one embodiment, when the processor executes the computer program, it also performs the following steps: generating a fitting curve of the reactivity value and time of the nuclear reactor based on the neutron data sequence of each segment of the control rod; and sending the fitting curve, the differential value of each control rod, and the integral value of the control rod to a display device.

[0150] In one embodiment, a computer program product is provided, including a computer program that, when executed by a processor, performs the following steps: When the nuclear reactor is in a preset state, control rods of the nuclear reactor are moved based on preset rod positions; the preset state includes the nuclear reactor's reactivity value reaching a reactivity threshold; for each rod position of the control rod, a neutron data sequence of the nuclear reactor is acquired, and the differential value of the control rod corresponding to each rod position is determined based on the neutron data sequence; the differential value of the control rod corresponding to each rod position is multiplied by the number of steps and then summed to obtain the integral value of the control rod; the differential value and the integral value of the control rod are used for reactivity control and to ensure the reactor's shutdown margin.

[0151] In one embodiment, when the processor executes the computer program, it further performs the following steps: acquiring multiple neutron flux densities of the nuclear reactor within a target time period; determining multiple reactivity values ​​of the nuclear reactor within the target time period based on each neutron flux density and the target time period; and determining a neutron data sequence based on each reactivity value and the target time period.

[0152] In one embodiment, when the processor executes the computer program, it further performs the following steps: querying the first reactivity value corresponding to the initial time in the first neutron data, and determining the second reactivity value based on the second neutron data; and determining the differential value of the control rod based on the first reactivity value and the second reactivity value.

[0153] In one embodiment, the processor, when executing the computer program, also performs the following steps: controlling the control rods to be in a fully extended state and continuously reducing the loop temperature of the nuclear reactor at a preset rate until the reactivity value reaches the reactivity threshold.

[0154] In one embodiment, the processor, when executing the computer program, also performs the following steps: continuously reducing the loop temperature of the nuclear reactor at a preset rate, and controlling the control rods to be inserted based on preset rod positions.

[0155] In one embodiment, the processor, while executing the computer program, also performs the following steps: controlling the control rods to be in a fully deployed state and reducing the loop temperature of the nuclear reactor until the reactivity value reaches the reactivity threshold.

[0156] In one embodiment, when the processor executes the computer program, it further performs the following steps: controlling the control rod to be inserted based on a preset rod position, and reducing the circuit temperature until the reactivity value reaches the reactivity threshold after the rate of change of the reactivity value is less than the rate of change threshold.

[0157] In one embodiment, when the processor executes the computer program, it also performs the following steps: determining the isothermal temperature coefficient of the nuclear reactor based on the neutron data sequence corresponding to each segment of the control rod; and sending the isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod to a display device.

[0158] In one embodiment, when the processor executes the computer program, it also performs the following steps: generating a fitting curve of the reactivity value and time of the nuclear reactor based on the neutron data sequence of each segment of the control rod; and sending the fitting curve, the differential value of each control rod, and the integral value of the control rod to a display device.

[0159] It should be noted that the data involved in this application (including but not limited to data used for analysis, data stored, data displayed, etc.) are all information and data authorized by the user or fully authorized by all parties, and the collection, use and processing of the relevant data must comply with relevant regulations.

[0160] Those skilled in the art will understand that all or part of the processes in the methods of the above embodiments can be implemented by a computer program instructing related hardware. The computer program can be stored in a non-volatile computer-readable storage medium, and when executed, it can include the processes of the embodiments of the above methods. Any references to memory, databases, or other media used in the embodiments provided in this application can include at least one of non-volatile memory and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM). The databases involved in the embodiments provided in this application may include at least one type of relational database and non-relational database. Non-relational databases may include, but are not limited to, blockchain-based distributed databases. The processors involved in the embodiments provided in this application may be general-purpose processors, central processing units, graphics processing units, digital signal processors, programmable logic devices, quantum computing-based data processing logic devices, artificial intelligence (AI) processors, etc., and are not limited to these.

[0161] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this application.

[0162] The embodiments described above are merely illustrative of several implementation methods of this application, and while the descriptions are specific and detailed, they should not be construed as limiting the scope of this patent application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this application should be determined by the appended claims.

Claims

1. A method for measuring the calculus value of control rods in a nuclear reactor, characterized in that, The method includes: When the nuclear reactor is in a preset state, the control rods controlling the nuclear reactor move based on preset rod positions; the preset state includes when the reactivity value of the nuclear reactor reaches a reactivity threshold. For each segment of the control rod, the neutron data sequence of the nuclear reactor is obtained, and the differential value of the control rod corresponding to each segment of the control rod is determined based on the neutron data sequence. The differential value of the control rod corresponding to each rod position is multiplied by the number of steps and then summed to obtain the integral value of the control rod. The differential value and the integral value of the control rod are used for reactivity control and to ensure the reactor shutdown margin.

2. The method according to claim 1, characterized in that, The acquisition of the neutron data sequence of the nuclear reactor includes: Obtain multiple neutron flux densities of the nuclear reactor within a target time period; Based on the neutron flux density and the target time period, determine multiple reactivity values ​​of the nuclear reactor within the target time period; The neutron data sequence is determined based on the reactivity values ​​and the target time period.

3. The method according to claim 1, characterized in that, The neutron data sequence includes first neutron data during the movement of the control rod, and second neutron data during the process of the nuclear reactor returning to the preset state. Determining the differential value of the control rod corresponding to each segment of the control rod based on the neutron data sequence includes: Query the first reactivity value corresponding to the initial time in the first neutron data, and determine the second reactivity value based on the second neutron data; The differential value of the control rod is determined based on the first reactivity value and the second reactivity value.

4. The method according to claim 1, characterized in that, The reactivity value of the nuclear reactor is adjusted to the reactivity threshold in the following manner: The control rod is kept in a fully extended state, and the loop temperature of the nuclear reactor is continuously reduced at a preset rate until the reactivity value reaches the reactivity threshold. The control rods controlling the nuclear reactor move based on preset rod positions, including: The loop temperature of the nuclear reactor is continuously reduced at a preset rate, and the control rods are inserted based on preset positions.

5. The method according to claim 1, characterized in that, The reactivity value of the nuclear reactor is adjusted to the reactivity threshold in the following manner: The control rod is kept in a fully extended state, and the loop temperature of the nuclear reactor is reduced until the reactivity value reaches the reactivity threshold. The control rods controlling the nuclear reactor move based on preset rod positions, including: The control rod is inserted based on a preset rod position, and after the rate of change of the reactivity value is less than the rate of change threshold, the circuit temperature is reduced until the reactivity value reaches the reactivity threshold.

6. The method according to claim 1, characterized in that, The method further includes: The isothermal temperature coefficient of the nuclear reactor is determined based on the neutron data sequence corresponding to each segment of the control rod. The isothermal temperature coefficient, the differential value of each control rod, and the integral value of the control rod are sent to the display device.

7. The method according to claim 1, characterized in that, The method further includes: Based on the neutron data sequence of each segment of the control rod, a fitting curve of the reactivity value and time of the nuclear reactor is generated. The fitted curve, the differential value of each control bar, and the integral value of the control bar are sent to the display device.

8. The method according to claim 1, characterized in that, The preset state also includes: The number of neutrons generated and the number of neutrons consumed in the nuclear reactor are the same, and / or the core temperature of the nuclear reactor reaches a temperature threshold.

9. The method according to any one of claims 1-8, characterized in that, The method is applied to the control rod control equipment of a nuclear reactor, which includes a boron-free thermal neutron reactor in the coolant.

10. A device for measuring the calculus value of control rods in a nuclear reactor, characterized in that, The device includes: The control rod control module is used to control the control rods of the nuclear reactor to move based on a preset rod position when the nuclear reactor is in a preset state; the preset state includes when the reactivity value of the nuclear reactor reaches a reactivity threshold. The control rod differential value acquisition module is used to acquire the neutron data sequence of the nuclear reactor for each segment of the control rod, and determine the control rod differential value corresponding to each segment of the control rod based on the neutron data sequence. The control rod integral value acquisition module is used to multiply the differential value of the control rod corresponding to each rod position by the number of steps and then sum them to obtain the control rod integral value of the control rod; the differential value and the integral value of the control rod are used for reactive control and to ensure the reactor shutdown margin.

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