Methods, devices, and circuits for monitoring and diagnosing control rod positions in high-temperature gas-cooled reactors

By calculating and diagnosing the positional deviation of the control rods in high-temperature gas-cooled reactors, the problems of inaccurate monitoring and cumbersome fault diagnosis in existing technologies have been solved, enabling real-time monitoring and rapid fault location, thereby improving the availability and nuclear safety of nuclear power units.

CN115691846BActive Publication Date: 2026-03-06HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER CO LTD
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Patent Information

Application Number
CN202211343713.9
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2022-10-31
Publication Date
2026-03-06
Estimated Expiration
2042-10-31

AI Technical Summary

Technical Problem

Existing technologies cannot accurately monitor the consistency between the actual operation of the control rods in high-temperature gas-cooled reactors and the expected requirements in real time. Furthermore, the process of troubleshooting fault points is cumbersome and time-consuming, resulting in low availability of nuclear power units and potential nuclear safety hazards.

Method used

By using the reactor power control system, stepper motor driver, and rod position measurement device, the target expected rod position and actual rod position are calculated, the rod position deviation is determined, and fault diagnosis is performed on the reactor power control system, stepper motor driver, rod position measurement device, and stepper motor to quickly locate the fault point.

Benefits of technology

This enabled real-time monitoring of the consistency between the control rod actions and expected requirements, rapid troubleshooting, improved the availability of nuclear power units, and ensured the nuclear safety of the reactor.

✦ Generated by Eureka AI based on patent content.

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Abstract

This disclosure provides a method, apparatus, and circuit for monitoring and diagnosing the position of control rods in a high-temperature gas-cooled reactor. The control rods are raised and lowered via a reactor power control system, a stepper motor driver, and a stepper motor, and their actual positions are measured by a rod position measuring device. The method includes: calculating the target expected position of the control rod based on read pulse feedback values; obtaining the actual position of the control rod; calculating the position deviation based on the target expected position and the actual position; determining whether the position deviation exceeds a preset limit; if so, setting the control rod corresponding to the position deviation as an abnormal rod; otherwise, setting the control rod corresponding to the position deviation as a normal rod; and performing fault diagnosis on the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor based on the abnormal and normal rods to determine the fault point. Real-time monitoring of the consistency between the actual control rod movement and the expected requirements is also provided.
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Description

Technical Field

[0001] The embodiments disclosed herein belong to the technical field of high-temperature gas-cooled reactor control rods, specifically relating to a method, apparatus, and circuit for monitoring the position and diagnosing faults of high-temperature gas-cooled reactor control rods. Background Technology

[0002] The high-temperature gas-cooled reactor nuclear power plant demonstration project consists of two reactors driving one steam turbine generator unit, with each reactor having 24 control rods. Control rods are a crucial means of controlling reactor reactivity; whether the control rods are precisely raised or lowered according to predetermined requirements directly affects the precise control of the unit's nuclear power. Current technology cannot accurately monitor the consistency between the actual movement of the control rods and the expected requirements in real time. When the control rod position deviation exceeds the limit, the process of troubleshooting is cumbersome, time-consuming, and labor-intensive, resulting in low availability of the nuclear power unit and certain potential nuclear safety hazards. Summary of the Invention

[0003] The embodiments disclosed herein aim to at least solve one of the technical problems existing in the prior art, and provide a method, apparatus, and circuit for monitoring the position of control rods and diagnosing faults in high-temperature gas-cooled reactors.

[0004] On one hand, embodiments of this disclosure provide a method for monitoring and diagnosing the position of control rods in a high-temperature gas-cooled reactor. The control rods are raised and lowered via a reactor power control system, a stepper motor driver, and a stepper motor, and their actual positions are measured by a rod position measuring device. The method includes:

[0005] The target expected position of the control rod is calculated based on the read pulse feedback value.

[0006] Obtain the actual position of the control rod;

[0007] The rod position deviation is calculated based on the expected rod position and the actual rod position.

[0008] Determine whether the rod position deviation exceeds a preset limit. If so, set the control rod corresponding to the rod position deviation as an abnormal rod; otherwise, set the control rod corresponding to the rod position deviation as a normal rod.

[0009] Based on the abnormal rod and the normal rod, fault diagnosis is performed on the reactor power control system, stepper motor driver, rod position measuring device and stepper motor to determine the fault point.

[0010] Optionally, fault diagnosis of the reactor power control system includes the following steps:

[0011] Perform the rod operation according to the set rod limit value of the abnormal rod;

[0012] Calculate the actual expected position of the abnormal rod based on the initial position of the abnormal rod and the limit value of the moving rod;

[0013] Determine whether the actual expected position of the abnormal rod is consistent with the target expected position of the abnormal rod; if they are consistent, the reactor power control system is determined to be fault-free; if they are inconsistent, the reactor power control system is determined to be faulty.

[0014] Optionally, the fault diagnosis of the stepper motor driver includes the following steps:

[0015] Interchange the stepper motor driver corresponding to the normal bar with the stepper motor driver corresponding to the abnormal bar;

[0016] Perform rod manipulation on the normal rod and the abnormal rod respectively, and determine whether the rod position deviation of each rod exceeds the preset limit;

[0017] If the position deviation of the normal bar does not exceed the preset limit, and the position deviation of the abnormal bar exceeds the preset limit, then the stepper motor driver corresponding to the abnormal bar is determined to be fault-free.

[0018] If the position deviation of the normal bar exceeds the preset limit, and the position deviation of the abnormal bar does not exceed the preset limit, then the stepper motor driver corresponding to the abnormal bar is determined to be faulty.

[0019] Optionally, the fault diagnosis of the rod position measuring device includes the following steps:

[0020] Interchange the rod position measuring device corresponding to the normal rod with the rod position measuring device corresponding to the abnormal rod;

[0021] Perform rod manipulation on the normal rod and the abnormal rod respectively, and determine whether the rod position deviation of each rod exceeds the preset limit;

[0022] If the position deviation of the normal bar does not exceed the preset limit, and the position deviation of the abnormal bar exceeds the preset limit, then the bar position measuring device corresponding to the abnormal bar is determined to be fault-free.

[0023] If the position deviation of the normal bar exceeds the preset limit, while the position deviation of the abnormal bar does not exceed the preset limit, then the position measuring device corresponding to the abnormal bar is determined to be faulty.

[0024] Optionally, the fault diagnosis of the stepper motor includes the following steps:

[0025] Interchange the stepper motor corresponding to the normal bar with the stepper motor corresponding to the abnormal bar;

[0026] Perform rod manipulation on the normal rod and the abnormal rod respectively, and determine whether the rod position deviation of each rod exceeds the preset limit;

[0027] If the position deviation of the normal bar does not exceed the preset limit, and the position deviation of the abnormal bar exceeds the preset limit, then the stepper motor corresponding to the abnormal bar is determined to be fault-free.

[0028] If the position deviation of the normal bar exceeds the preset limit, and the position deviation of the abnormal bar does not exceed the preset limit, then the stepper motor corresponding to the abnormal bar is determined to be faulty.

[0029] Optionally, the fault diagnosis of the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor includes:

[0030] Fault diagnosis was performed sequentially on the reactor power control system, the stepper motor driver, and the rod position measuring device.

[0031] If the reactor power control system, the stepper motor driver, and the rod position measuring device are all functioning correctly, then the stepper motor is determined to be faulty.

[0032] On the other hand, embodiments of this disclosure provide a control rod position monitoring and fault diagnosis device for a high-temperature gas-cooled reactor. The control rod is raised and lowered via a reactor power control system, a stepper motor driver, and a stepper motor, and its position is measured via a rod position measuring device. The device includes:

[0033] The calculation module is used to calculate the target expected position of the control rod based on the read pulse feedback value;

[0034] The acquisition module is used to acquire the actual position of the control rod;

[0035] The calculation module is also used to calculate the rod position deviation based on the target expected rod position and the actual rod position;

[0036] The judgment module is used to determine whether the rod position deviation exceeds a preset limit. If it does, the control rod corresponding to the rod position deviation is set as an abnormal rod; otherwise, the control rod corresponding to the rod position deviation is set as a normal rod.

[0037] The diagnostic module is used to perform fault diagnosis on the reactor power control system, stepper motor driver, rod position measuring device and stepper motor based on the abnormal rod and the normal rod, so as to determine the fault point.

[0038] On the other hand, embodiments of this disclosure provide a control rod position monitoring and fault diagnosis device for a high-temperature gas-cooled reactor. The device includes a reactor power control system, a stepper motor driver, a stepper motor, and a rod position measuring device. The control rod is raised and lowered via the reactor power control system, the stepper motor driver, and the stepper motor.

[0039] The reactor power control system is used to calculate the target expected position of the control rod based on the read pulse feedback value.

[0040] The rod position measuring device is used to measure the actual position of the control rod;

[0041] The reactor power control system is also used for:

[0042] The rod position deviation is calculated based on the expected rod position and the actual rod position.

[0043] Determine whether the rod position deviation exceeds a preset limit. If so, set the control rod corresponding to the rod position deviation as an abnormal rod; otherwise, set the control rod corresponding to the rod position deviation as a normal rod.

[0044] Based on the abnormal rod and the normal rod, fault diagnosis is performed on the reactor power control system, stepper motor driver, rod position measuring device and stepper motor to determine the fault point.

[0045] On the other hand, embodiments of this disclosure provide a logic circuit for monitoring the position of control rods in a high-temperature gas-cooled reactor. The logic circuit includes a first selection module, a second selection module, a third selection module, a first subtraction module, a second subtraction module, a division module, and an addition module; wherein,

[0046] The first input terminal of the first selection module is electrically connected to the rotation control signal terminal, the second input terminal of the first selection module is electrically connected to the pulse readback signal terminal, and the output terminal of the first selection module is electrically connected to its third input terminal and the second input terminal of the first subtraction module, respectively.

[0047] The first input terminal of the second selection module is electrically connected to the rotation control signal terminal, the second input terminal of the second selection module is electrically connected to the actual rod position signal terminal, and the output terminal of the second selection module is electrically connected to its third input terminal and the second input terminal of the addition module, respectively.

[0048] The first input terminal of the third selection module is electrically connected to the rotation control signal terminal, the third input terminal of the third selection module is electrically connected to the output terminal of the addition module, and the output terminal of the third selection module is electrically connected to its second input terminal and the expected rod position signal terminal, respectively.

[0049] The first input terminal of the first subtraction module is electrically connected to the pulse readback signal terminal, the output terminal of the first subtraction module is electrically connected to the first input terminal of the division module, the second input terminal of the division module is electrically connected to the pulse equivalent output terminal, and the output terminal of the division module is electrically connected to the first input terminal of the addition module.

[0050] The first input terminal of the second subtraction module is electrically connected to the expected rod position signal terminal, the second input terminal of the second subtraction module is electrically connected to the actual rod position signal terminal, and the output terminal of the second subtraction module is electrically connected to the rod position deviation signal terminal.

[0051] On the other hand, embodiments of this disclosure provide a method for monitoring the position of control rods in a high-temperature gas-cooled reactor, employing the logic circuit described above, the method comprising:

[0052] Upon receiving a high-level rotation control signal output from the rotation control signal terminal, the logic circuit executes the following specific steps:

[0053] The output of the first selection module locks the readback value of the control rod's moving rod pulse, and the output of the second selection module locks the actual position of the control rod's moving rod.

[0054] The first subtraction module subtracts the real-time pulse readback value from the pulse readback signal terminal from the pulse readback value before the moving rod to obtain the difference between the two; and the division module divides the difference between the two by the pulse equivalent to obtain the target expected rod position change.

[0055] The addition module adds the actual position of the moving rod before the target rod to the change in the target expected position to obtain the target expected position.

[0056] The second subtraction module subtracts the expected target rod position from the actual rod position signal from the actual rod position signal terminal to obtain the rod position deviation;

[0057] Upon receiving a low-level rotation control signal output from the rotation control signal terminal, the logic circuit executes the following steps:

[0058] The output of the third selection module locks the target position of the moving rod.

[0059] The high-temperature gas-cooled reactor control rod position monitoring and fault diagnosis method, device, and circuit of the present disclosure can monitor the consistency between the actual operation of the control rod and the expected requirements in real time, and quickly locate the fault point when the rod position deviation exceeds the limit, thereby improving the availability of nuclear power units and ensuring the nuclear safety of the reactor. Attached Figure Description

[0060] Figure 1This is a schematic diagram of the control rod system interface of a method for monitoring and diagnosing control rod positions in a high-temperature gas-cooled reactor according to an embodiment of the present disclosure.

[0061] Figure 2 This is a flowchart of a method for monitoring and diagnosing the position of control rods in a high-temperature gas-cooled reactor, according to another embodiment of this disclosure.

[0062] Figure 3 This is a logic circuit diagram for monitoring the position of control rods in a high-temperature gas-cooled reactor, according to another embodiment of the present disclosure.

[0063] Figure 4 A fault diagnosis flowchart for a reactor power control system according to another embodiment of this disclosure;

[0064] Figure 5 A flowchart illustrating the fault diagnosis of a stepper motor driver according to another embodiment of this disclosure;

[0065] Figure 6 This is a flowchart illustrating the fault diagnosis of a rod position measuring device according to another embodiment of the present disclosure;

[0066] Figure 7 This is a flowchart illustrating the fault diagnosis process of a stepper motor according to another embodiment of the present disclosure. Detailed Implementation

[0067] To enable those skilled in the art to better understand the technical solutions of this disclosure, the disclosure will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0068] The method for monitoring and diagnosing control rod position deviation in a high-temperature gas-cooled reactor disclosed herein is based on, as in, Figure 1 The control stick system interface shown is as follows: Figure 1 As shown, the reactor power control system 120 outputs stepping pulse signals, rotation control signals, and steering control signals to the stepping motor driver 130 through the stepping motor control module 121. Under the combined action of the stepping pulse signals, rotation control signals, and steering control signals, the stepping motor driver 130 controls the stepping motor to rotate forward or backward, and then drives the control rod 110 to rise or fall through the transmission device. The transmission device can be set as a chain.

[0069] It should be noted that the rotation control signal controls whether the stepper motor 140 rotates or not. When the rotation control signal output is a high-level rotation control signal, that is, when the rotation control signal output is 1, the stepper motor 140 can rotate according to the step pulse signal. When the rotation control signal output is a low-level rotation control signal, that is, when the rotation control signal output is 0, the stepper motor 140 will not rotate even if there is a step pulse signal.

[0070] The steering control signal controls the rotation direction of the stepper motor 140. When the steering control signal output is a high-level steering control signal (i.e., the steering control signal output is 1), the stepper motor 140 rotates in the forward direction. When the steering control signal output is a low-level steering control signal (i.e., the steering control signal output is 0), the stepper motor 140 rotates in the reverse direction.

[0071] When the rotation control signal output is 1, the stepper pulse signal can cause the stepper motor 140 to rotate a given number of steps in the direction specified by the steering control signal. If the stepper motor control module does not output a stepper pulse signal, then even if the rotation control signal output is 1 and the steering control signal output is 1, the stepper motor 140 will not operate.

[0072] The control rod 110 is raised and lowered via the reactor power control system 120, stepper motor driver 130, and stepper motor 140, and its position is measured via the rod position measuring device 150. The following will be combined with... Figure 2 This disclosure describes a method for monitoring and diagnosing the position of control rods in a high-temperature gas-cooled reactor, comprising the following steps:

[0073] Step S100: Calculate the target expected position of the control rod based on the read pulse feedback value.

[0074] Specifically, such as Figure 1 As shown, the reactor power control system 120 includes a stepper motor control module 121. The stepper motor control module 121 has a pulse output readback function, which can continuously count the actual output stepper pulses, such as adding and subtracting the output forward and reverse pulses respectively. When both the stepper motor driver 130 and the stepper motor 140 are working normally, the bidirectional cumulative count of the stepper pulses by the stepper motor control module 121 can reflect the actual position of the control rod after it has been raised or lowered.

[0075] If the rotation control signal is 0, the control rod 110 does not move. If the rotation control signal is 1 and the direction control signal controls the stepper motor 140 to rotate forward, the rod movement is a lifting motion, and the target expected rod position of the control rod 110 is the sum of its actual rod position before lifting and the rod position change corresponding to the number of stepping pulses issued by the stepper motor control module 121. If the rotation control signal is 1 and the direction control signal controls the stepper motor 140 to rotate in reverse, the rod movement is a lowering motion, and the target expected rod position of the control rod 110 is the difference between its actual rod position before lowering and the rod position change corresponding to the number of stepping pulses issued by the stepper motor control module 121.

[0076] Step S200: Obtain the actual position of the control rod.

[0077] Specifically, such as Figure 1 As shown, the actual position of the control rod 110 is measured using the rod position measuring device 150. The device is simple in structure and easy to replace.

[0078] Step S300: Calculate the rod position deviation based on the target expected rod position and the actual rod position. This is based on... Figure 3 The logic circuit shown is as follows: Figure 3 As shown, the logic circuit for monitoring the position of control rods in a high-temperature gas-cooled reactor includes a first selection module, a second selection module, a third selection module, a first subtraction module, a second subtraction module, a division module, and an addition module. The first input terminal of the first selection module is electrically connected to the rotation control signal terminal, the second input terminal of the first selection module is electrically connected to the pulse readback signal terminal, and the output terminal of the first selection module is electrically connected to both its third input terminal and the second input terminal of the first subtraction module.

[0079] The first input terminal of the second selection module is electrically connected to the rotation control signal terminal, the second input terminal of the second selection module is electrically connected to the actual rod position signal terminal, and the output terminal of the second selection module is electrically connected to its third input terminal and the second input terminal of the addition module. The first input terminal of the third selection module is electrically connected to the rotation control signal terminal, the third input terminal of the third selection module is electrically connected to the output terminal of the addition module, and the output terminal of the third selection module is electrically connected to its second input terminal and the expected rod position signal terminal.

[0080] The first input terminal of the first subtraction module is electrically connected to the pulse readback signal terminal, the output terminal of the first subtraction module is electrically connected to the first input terminal of the division module, the second input terminal of the division module is electrically connected to the pulse equivalent output terminal, and the output terminal of the division module is electrically connected to the first input terminal of the addition module. The first input terminal of the second subtraction module is electrically connected to the expected rod position signal terminal, the second input terminal of the second subtraction module is electrically connected to the actual rod position signal terminal, and the output terminal of the second subtraction module is electrically connected to the rod position deviation signal terminal.

[0081] Specifically, such as Figure 3As shown, when a high-level rotation control signal is received from the rotation control signal terminal, the logic circuit executes the following specific steps: the output terminal of the first selection module locks the pulse readback value before the control rod moves, and the output terminal of the second selection module locks the actual rod position before the control rod moves. The first subtraction module subtracts the real-time pulse readback value from the pulse readback signal terminal from the pulse readback value before the control rod moves to obtain the difference between the two; and the division module divides the difference between the two by the pulse equivalent to obtain the target expected rod position change. The addition module adds the actual rod position before the control rod moves to the target expected rod position change to obtain the target expected rod position. The second subtraction module subtracts the target expected rod position from the actual rod position from the actual rod position signal terminal to obtain the rod position deviation. It should be noted that the pulse equivalent is the number of pulses corresponding to the control rod moving a unit distance.

[0082] When the low-level rotation control signal is received from the rotation control signal terminal, the logic circuit performs the following steps: the output terminal of the third selection module locks the target expected position of the moving rod.

[0083] The above logic is repeated, and the target position of the control rod is recalculated for each control rod movement. The deviation between the actual position and the target position is also recalculated. It's easy to understand that the current position deviation only indicates whether there is an anomaly during this rod movement; the position deviation does not accumulate with multiple rod movements. Applying this logic circuit allows for real-time monitoring of the consistency between the actual control rod movement and the expected requirements.

[0084] Step S400: Determine whether the rod position deviation exceeds a preset limit. If so, set the control rod corresponding to the rod position deviation as an abnormal rod; otherwise, set the control rod corresponding to the rod position deviation as a normal rod.

[0085] Specifically, in this step, the obtained rod position deviation is judged. If the rod position deviation exceeds a preset limit, the control rod is an abnormal rod. If the rod position deviation does not exceed the preset limit, the control rod is a normal rod. It should be noted that the high-temperature gas-cooled reactor has a total of 24 control rods, but other numbers of control rods can also be set. This embodiment does not limit this. Each control rod is equipped with a stepper motor control module, a stepper motor driver, a stepper motor, and a rod position measuring device.

[0086] Step S500: Based on the abnormal rod and the normal rod, perform fault diagnosis on the reactor power control system, stepper motor driver, rod position measuring device and stepper motor to determine the fault point.

[0087] Specifically, in this step, based on the identified abnormal and normal rods, fault diagnosis is performed on the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor to determine the fault point.

[0088] As an example, such as Figure 4 As shown, the fault diagnosis of the reactor power control system includes the following steps: Executing a rod-moving operation according to the set rod-moving limit of the abnormal rod. Calculating the actual expected rod position of the abnormal rod based on its initial position and the rod-moving limit. Determining whether the actual expected rod position of the abnormal rod matches its target expected rod position. If they match, the reactor power control system is determined to be fault-free; otherwise, the reactor power control system is determined to be faulty.

[0089] As an example, such as Figure 5 As shown, the fault diagnosis of the stepper motor driver includes the following steps: Interchanging the stepper motor driver corresponding to the normal bar with the stepper motor driver corresponding to the abnormal bar. Performing a bar-moving operation on both the normal bar and the abnormal bar, and determining whether the bar position deviation of each exceeds the preset limit. If the bar position deviation of the normal bar does not exceed the preset limit, but the bar position deviation of the abnormal bar exceeds the preset limit, then the stepper motor driver corresponding to the abnormal bar is determined to be fault-free. If the bar position deviation of the normal bar exceeds the preset limit, but the bar position deviation of the abnormal bar does not exceed the preset limit, then the stepper motor driver corresponding to the abnormal bar is determined to be faulty.

[0090] As an example, such as Figure 6 As shown, the fault diagnosis of the rod position measuring device includes the following steps: Interchanging the rod position measuring device corresponding to the normal rod with the rod position measuring device corresponding to the abnormal rod. Performing a rod movement operation on both the normal rod and the abnormal rod, and determining whether the rod position deviation of each exceeds the preset limit. If the rod position deviation of the normal rod does not exceed the preset limit, but the rod position deviation of the abnormal rod exceeds the preset limit, then the rod position measuring device corresponding to the abnormal rod is determined to be fault-free. If the rod position deviation of the normal rod exceeds the preset limit, but the rod position deviation of the abnormal rod does not exceed the preset limit, then the rod position measuring device corresponding to the abnormal rod is determined to be faulty.

[0091] As an example, such as Figure 7As shown, the fault diagnosis of the stepper motor includes the following steps: Interchanging the stepper motor corresponding to the normal stepper and the stepper motor corresponding to the abnormal stepper. Performing a stepper operation on both the normal stepper and the abnormal stepper, and determining whether the position deviation of each exceeds a preset limit. If the position deviation of the normal stepper does not exceed the preset limit, but the position deviation of the abnormal stepper exceeds the preset limit, then the stepper motor corresponding to the abnormal stepper is determined to be fault-free. If the position deviation of the normal stepper exceeds the preset limit, but the position deviation of the abnormal stepper does not exceed the preset limit, then the stepper motor corresponding to the abnormal stepper is determined to be faulty.

[0092] The high-temperature gas-cooled reactor control rod position monitoring and fault diagnosis method disclosed herein can promptly identify whether the control rod position deviation exceeds a preset limit, allowing maintenance personnel to quickly locate the fault point and effectively improve the unit's availability.

[0093] For example, the fault diagnosis of the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor includes: sequentially diagnosing the reactor power control system, the stepper motor driver, and the rod position measuring device according to the method described above. If the reactor power control system, the stepper motor driver, and the rod position measuring device are all fault-free, then the stepper motor is determined to be faulty. Since the stepper motor is located within the pressure boundary of the primary loop of the high-temperature gas-cooled reactor, it is difficult to confirm the fault by swapping the stepper motor corresponding to the normal rod with the stepper motor corresponding to the abnormal rod as described above. It is also difficult to swap the stepper motors of the two control rods. Therefore, it is simpler and more time-saving to confirm whether the stepper motor is the fault point by checking it sequentially.

[0094] The high-temperature gas-cooled reactor control rod position monitoring and fault diagnosis method disclosed herein can monitor the consistency between the actual operation of the control rod and the expected requirements in real time, and quickly locate the fault point when the rod position deviation exceeds the limit, thereby improving the availability of nuclear power units and ensuring the nuclear safety of the reactor.

[0095] On the other hand, embodiments of this disclosure relate to a control rod position monitoring and fault diagnosis device for a high-temperature gas-cooled reactor. The control rod is raised and lowered via a reactor power control system, a stepper motor driver, and a stepper motor, and its position is measured by a rod position measuring device. The device includes: a calculation module for calculating the target expected position of the control rod based on read pulse values; and an acquisition module for acquiring the actual position of the control rod. The calculation module is further configured to calculate the rod position deviation based on the target expected position and the actual position.

[0096] The judgment module is used to determine whether the rod position deviation exceeds a preset limit. If so, the control rod corresponding to the rod position deviation is set as an abnormal rod; otherwise, the control rod corresponding to the rod position deviation is set as a normal rod. The diagnosis module is used to perform fault diagnosis on the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor based on the abnormal rod and the normal rod, in order to determine the fault point.

[0097] The high-temperature gas-cooled reactor control rod position monitoring and fault diagnosis device of this disclosure can monitor the consistency between the actual operation of the control rod and the expected requirements in real time, and quickly locate the fault point when the rod position deviation exceeds the limit, thereby improving the availability of nuclear power units and ensuring the nuclear safety of the reactor.

[0098] On the other hand, embodiments of this disclosure relate to a control rod position monitoring and fault diagnosis device for a high-temperature gas-cooled reactor. The device includes a reactor power control system, a stepper motor driver, a stepper motor, and a rod position measuring device. The control rod is raised and lowered via the reactor power control system, the stepper motor driver, and the stepper motor. The reactor power control system is used to calculate the target expected position of the control rod based on read pulse feedback values. The rod position measuring device is used to measure the actual position of the control rod.

[0099] The reactor power control system is further configured to: calculate the rod position deviation based on the target expected rod position and the actual rod position; determine whether the rod position deviation exceeds a preset limit; if so, set the control rod corresponding to the rod position deviation as an abnormal rod; otherwise, set the control rod corresponding to the rod position deviation as a normal rod; and perform fault diagnosis on the reactor power control system, stepper motor driver, rod position measuring device, and stepper motor based on the abnormal rod and the normal rod to determine the fault point.

[0100] The high-temperature gas-cooled reactor control rod position monitoring and fault diagnosis device of this disclosure can monitor the consistency between the actual operation of the control rod and the expected requirements in real time, and quickly locate the fault point when the rod position deviation exceeds the limit, thereby improving the availability of nuclear power units and ensuring the nuclear safety of the reactor.

[0101] It is understood that the above embodiments are merely exemplary embodiments used to illustrate the principles of this disclosure, and this disclosure is not limited thereto. For those skilled in the art, various modifications and improvements can be made without departing from the spirit and substance of this disclosure, and these modifications and improvements are also considered to be within the scope of protection of this disclosure.

Claims

1. A method of monitoring and diagnosing a fault of a control rod position of a high temperature gas cooled reactor, the control rod is raised and lowered by a reactor power control system, a stepper motor driver and a stepper motor, and an actual rod position is measured by a rod position measuring device, characterized in that, The method comprises: calculating a target expected rod position of the control rod according to the read pulse back read value; obtaining an actual rod position of the control rod; calculating a rod position deviation according to the target expected rod position and the actual rod position; judging whether the rod position deviation exceeds a preset limit value, and setting the control rod corresponding to the rod position deviation as an abnormal rod if the rod position deviation exceeds the preset limit value, or setting the control rod corresponding to the rod position deviation as a normal rod if the rod position deviation does not exceed the preset limit value; performing fault diagnosis on a reactor power control system, a stepper motor driver, a rod position measuring device and a stepper motor according to the abnormal rod and the normal rod to determine a fault point; the fault diagnosis of the stepper motor driver comprises the following steps: interchanging the stepper motor driver corresponding to the normal rod with the stepper motor driver corresponding to the abnormal rod; performing rod movement operation on the normal rod and the abnormal rod respectively, and judging whether the rod position deviation of each of the normal rod and the abnormal rod exceeds the preset limit value; if the rod position deviation of the normal rod does not exceed the preset limit value and the rod position deviation of the abnormal rod exceeds the preset limit value, it is determined that the stepper motor driver corresponding to the abnormal rod is not faulty; if the rod position deviation of the normal rod exceeds the preset limit value and the rod position deviation of the abnormal rod does not exceed the preset limit value, it is determined that the stepper motor driver corresponding to the abnormal rod is faulty.

2. The method of claim 1, wherein, the fault diagnosis of the reactor power control system comprises the following steps: performing rod movement operation according to a set rod movement limit value of the abnormal rod; calculating an actual expected rod position of the abnormal rod according to an initial rod position of the abnormal rod and the rod movement limit value; judging whether the actual expected rod position of the abnormal rod is consistent with a target expected rod position of the abnormal rod; if consistent, it is determined that the reactor power control system is not faulty; if not consistent, it is determined that the reactor power control system has a fault.

3. The method of claim 1, wherein, the fault diagnosis of the rod position measuring device comprises the following steps: interchanging the rod position measuring device corresponding to the normal rod with the rod position measuring device corresponding to the abnormal rod; performing rod movement operation on the normal rod and the abnormal rod respectively, and judging whether the rod position deviation of each of the normal rod and the abnormal rod exceeds the preset limit value; if the rod position deviation of the normal rod does not exceed the preset limit value and the rod position deviation of the abnormal rod exceeds the preset limit value, it is determined that the rod position measuring device corresponding to the abnormal rod is not faulty; if the rod position deviation of the normal rod exceeds the preset limit value and the rod position deviation of the abnormal rod does not exceed the preset limit value, it is determined that the rod position measuring device corresponding to the abnormal rod is faulty.

4. The method of claim 1, wherein, the fault diagnosis of the stepper motor comprises the following steps: interchanging the stepper motor corresponding to the normal rod with the stepper motor corresponding to the abnormal rod; performing rod movement operation on the normal rod and the abnormal rod respectively, and judging whether the rod position deviation of each of the normal rod and the abnormal rod exceeds the preset limit value; if the rod position deviation of the normal rod does not exceed the preset limit value and the rod position deviation of the abnormal rod exceeds the preset limit value, it is determined that the stepper motor corresponding to the abnormal rod is not faulty; If the rod position deviation of the normal rod exceeds the preset limit value, and the rod position deviation of the abnormal rod does not exceed the preset limit value, it is determined that the step motor corresponding to the abnormal rod is faulty.

5. The method of claim 1 to 4, characterized in that, The reactor power control system, the step motor driver, the rod position measuring device and the step motor are diagnosed for faults, including: The reactor power control system, the step motor driver and the rod position measuring device are sequentially diagnosed for faults; If the reactor power control system, the step motor driver and the rod position measuring device are all fault-free, it is determined that the step motor is faulty.

6. A device for monitoring and failure diagnosis of a control rod position of a high temperature gas cooled reactor, the control rod being raised and lowered by a reactor power control system, a stepping motor driver and a stepping motor, and the control rod position being measured by a rod position measuring device, characterized in that, The device includes: A calculation module configured to calculate a target expected rod position of the control rod according to a read pulse readback value; An acquisition module configured to acquire an actual rod position of the control rod; The calculation module is further configured to calculate a rod position deviation according to the target expected rod position and the actual rod position; A judgment module configured to judge whether the rod position deviation exceeds a preset limit value, and if so, set the control rod corresponding to the rod position deviation as an abnormal rod, and if not, set the control rod corresponding to the rod position deviation as a normal rod; A diagnosis module configured to diagnose the reactor power control system, the step motor driver, the rod position measuring device and the step motor for faults according to the abnormal rod and the normal rod, to determine a fault point; The diagnosis module is specifically further configured to: interchange the step motor driver corresponding to the normal rod with the step motor driver corresponding to the abnormal rod; perform a rod movement operation on the normal rod and the abnormal rod respectively, and judge whether the rod position deviation of each of the two exceeds the preset limit value; if the rod position deviation of the normal rod does not exceed the preset limit value, and the rod position deviation of the abnormal rod exceeds the preset limit value, it is determined that the step motor driver corresponding to the abnormal rod is fault-free; if the rod position deviation of the normal rod exceeds the preset limit value, and the rod position deviation of the abnormal rod does not exceed the preset limit value, it is determined that the step motor driver corresponding to the abnormal rod is faulty.

7. A device for monitoring and fault diagnosis of a control rod position of a high temperature gas cooled reactor, characterized in that The device includes a reactor power control system, a step motor driver, a step motor and a rod position measuring device, and the control rod is controlled to ascend or descend via the reactor power control system, the step motor driver and the step motor; wherein, The reactor power control system is configured to calculate a target expected rod position of the control rod according to a read pulse readback value; The rod position measuring device is configured to measure an actual rod position of the control rod; The reactor power control system is further configured to: calculate a rod position deviation according to the target expected rod position and the actual rod position; judge whether the rod position deviation exceeds a preset limit value, and if so, set the control rod corresponding to the rod position deviation as an abnormal rod, and if not, set the control rod corresponding to the rod position deviation as a normal rod; diagnose the reactor power control system, the step motor driver, the rod position measuring device and the step motor for faults according to the abnormal rod and the normal rod, to determine a fault point; The reactor power control system is specifically further configured to: interchange the step motor driver corresponding to the normal rod with the step motor driver corresponding to the abnormal rod; perform rod movement operation on the normal rod and the abnormal rod respectively, and determine whether the rod position deviation of each of the two rods exceeds the preset limit value; if the rod position deviation of the normal rod does not exceed the preset limit value, and the rod position deviation of the abnormal rod exceeds the preset limit value, it is determined that the step motor driver corresponding to the abnormal rod is not faulty; if the rod position deviation of the normal rod exceeds the preset limit value, and the rod position deviation of the abnormal rod does not exceed the preset limit value, it is determined that the step motor driver corresponding to the abnormal rod is faulty.

8. A logic circuit for monitoring a control rod position of a high temperature gas cooled reactor, characterized in that, The high-temperature gas cooled reactor control rod position monitoring and fault diagnosis device of claim 7, wherein the logic circuit comprises a first selection module, a second selection module, a third selection module, a first subtraction module, a second subtraction module, a division module, and an addition module. The first input end of the first selection module is electrically connected with the rotation control signal end, the second input end of the first selection module is electrically connected with the pulse readback signal end, and the output end of the first selection module is electrically connected with the third input end thereof and the second input end of the first subtraction module. The first input end of the second selection module is electrically connected with the rotation control signal end, the second input end of the second selection module is electrically connected with the actual rod position signal end, and the output end of the second selection module is electrically connected with the third input end thereof and the second input end of the addition module. The first input end of the third selection module is electrically connected with the rotation control signal end, the third input end of the third selection module is electrically connected with the output end of the addition module, and the output end of the third selection module is electrically connected with the second input end thereof and the expected rod position signal end. The first input end of the first subtraction module is electrically connected with the pulse readback signal end, the output end of the first subtraction module is electrically connected with the first input end of the division module, the second input end of the division module is electrically connected with the pulse equivalent output end, and the output end of the division module is electrically connected with the first input end of the addition module. The first input end of the second subtraction module is electrically connected with the expected rod position signal end, the second input end of the second subtraction module is electrically connected with the actual rod position signal end, and the output end of the second subtraction module is electrically connected with the rod position deviation signal end.

9. A method for monitoring the position of a control rod in a high-temperature gas-cooled reactor, characterized in that The logic circuit of claim 8, wherein the method comprises: Upon receiving a high-level rotation control signal output from the rotation control signal end, the logic circuit performs the following specific steps: The output end of the first selection module locks the pre-rod movement pulse readback value of the control rod, and the output end of the second selection module locks the pre-rod movement actual rod position of the control rod. The first subtraction module subtracts the real-time pulse readback value from the pulse readback signal end from the pre-rod movement pulse readback value to obtain a difference value therebetween, and the division module divides the difference value by the pulse equivalent to obtain a target expected rod position change amount. The addition module adds the actual rod position before the moving rod to the target expected rod position change amount to obtain a target expected rod position; The second subtraction module subtracts the actual rod position from the actual rod position signal end to obtain a rod position deviation; When receiving a low level rotation control signal output by the rotation control signal end, the logic circuit executes the following steps: The output end of the third selection module locks the target expected rod position of the moving rod this time.

Citation Information

Patent Citations

  • High-temperature gas cooled reactor control rod position monitoring method, device and equipment and storage medium

    CN115171930A