Nuclear power plant protection signal state real-time monitoring method
By creating communication and logic computing modules on a non-safety-grade platform, automated monitoring of nuclear power plant protection signal status was achieved, solving the problems of high labor costs and human error prevention, improving work efficiency and safety, and adapting to real-time response in complex production environments.
Patent Information
- Application Number
- CN202511558894.0
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-10-29
- Publication Date
- 2026-02-13
AI Technical Summary
Real-time monitoring of protection signal status in nuclear power plants faces challenges such as high labor costs, difficulty in preventing human error, and difficulty in risk control under complex production environments. Existing technologies cannot achieve automation and real-time response.
By adding communication cards and configuring communication protocols on a non-security platform, and creating interfaces, threshold calculation, logic calculation, and display modules, automated monitoring and intuitive display of signal status are achieved. Data interaction and logical judgment are performed between the IA platform FBM232 and the TRICONEX platform.
It has enabled automated monitoring of the protection signal status of nuclear power plants, reduced labor costs, reduced the risk of human error, improved work efficiency and safety, and adapted to real-time response in complex production environments.
Smart Images

Figure CN121530877A_ABST
Abstract
Description
Technical Field
[0001] This invention belongs to the field of nuclear power plant instrumentation and control technology, specifically relating to a method for real-time monitoring of the status of protection signals in nuclear power plants. Background Technology
[0002] The signals from reactor protection systems, safety injection systems, and safety spray systems in nuclear power plants are typically determined by a vote from measurements from three or four sensors. A logical action is triggered when a two-out-of-three or two-out-of-four condition is met, protecting the reactor and preventing radioactive leakage. However, incorrect production and maintenance activities leading to false triggering of this logic or equipment malfunction can cause severe economic losses and damage to nuclear safety-related equipment. During pre-maintenance work, to verify the availability of individual signal channels, each channel needs to be tested to confirm that its accuracy meets requirements. This work carries a significant risk: if one condition of the two-out-of-three or two-out-of-four logic is already met, blindly conducting tests at this point will trigger the logic.
[0003] To avoid the above situations, current pre-test confirmation is mainly achieved through manual inspection and comparison. The safety-grade DCS software platform TRICONEX cannot export current point values in real-time to a batch-processable format; it can only be viewed one by one. This presents the following problems: High labor costs: Signal points related to the same trigger logic are distributed across different channels, requiring multiple channels to be opened for each inspection, resulting in a large workload. Performing this work during refueling and overhaul periods in nuclear power plants, where manpower is already strained, requires significant manpower for signal inspection and comparison. High difficulty in preventing human error: Due to the complexity of the logic and the concealment of point information, human error is prone to occur, leading to missed or incorrect checks. Differences in knowledge and skill levels: Reactor protection systems are complex, and different personnel have varying levels of understanding and skill levels, with some unable to meet the work requirements. Complex production environment: The production environment is highly complex due to temporary instrument malfunctions, overlapping maintenance work windows, signal resets, and other critical test steps, making risk control through basic technical means extremely difficult. Summary of the Invention
[0004] This invention provides a real-time monitoring method for the status of protection signals in nuclear power plants. By capturing test-related signal information, performing calculations and logical judgments, the method presents the feasibility judgment results of the current test in an intuitive visual manner, and locates signals when there are risks in the test. This achieves the following objectives: automating test risk analysis and significantly reducing labor costs; automating signal status capture and significantly reducing skill requirements; and enabling real-time response and dynamic detection to cope with complex production environments.
[0005] To achieve the above objectives, the technical solution adopted by the present invention is as follows: A method for real-time monitoring of protection signal status in nuclear power plants, comprising the following steps: Step 1: Add the communication card to the non-security platform; Step 2: Configure the communication protocol and data address, and debug to establish communication between the non-security platform and the security platform; Step 3: Create an interface module on the non-secure platform to receive data, and add a threshold calculation module on the non-secure platform to perform threshold calculation; Step 4: Create a logic calculation module on a non-security platform to perform logic calculations, and create a quality bit judgment module to perform status judgments; Step 5: Add a display module to the non-security platform to display the results of quality bit and threshold comparison.
[0006] The communication card mentioned is the IA platform FBM232.
[0007] The security-grade platform mentioned is TRICONEX.
[0008] Establish communication points on the IA platform, establish a one-to-one correspondence between the storage location and the security level platform points that need to be monitored, and create an FDSI table.
[0009] The threshold calculation module and the safety-level platform location are set identically in terms of maximum design range, unit, and rate of change characteristic parameters.
[0010] The logic calculation module is close to the logic threshold of the safety-grade platform for generating reactor protection and dedicated actions, leaving a certain margin.
[0011] The quality position judgment module will trigger a display change in the event of communication loss, over-range measurement, or hardware failure, to indicate that there is an anomaly at the corresponding position.
[0012] The overrange configuration is consistent with the safety-grade platform, reflecting the actual state of the safety-grade platform's point quality trigger.
[0013] Step five: Display the visual screen of the nested design of the relevant modules. The first layer screen is a list of tests to be performed. The system is indexed according to the work content. Clicking on the work object in the list will jump to the second layer screen. The second layer screen displays the test point information for a single channel. The test name is at the bottom of the screen. Each element in the second layer screen is defined by the relevant point of the non-safety-level platform. Clicking on the element will display the relevant configuration information. After confirmation, it will jump to the specific screen of the corresponding point of the non-safety-level platform. The trend function can be called up to observe the real-time trend of signal quality or value.
[0014] Step 5: Before conducting a channel test, first enter the first-level screen to select the test. After clicking to jump to the second-level screen, verify the quality of the relevant signals and the threshold triggering status. If red is found, verify whether the conditions for starting the test are met. Otherwise, the abnormality must be eliminated before conducting the channel test.
[0015] The beneficial effects achieved by this invention are as follows: When conducting nuclear power plant protection signal channel tests, this invention first confirms the relevant signal status on the relevant screen of the non-safety-grade platform to ensure that the test can be carried out normally. If there is any abnormality, the relevant instruments are directly confirmed through the screen configuration information to confirm whether the conditions for carrying out the test are met. This eliminates the risks of disconnection or test overlap caused by on-site work, which can greatly improve work efficiency, reduce the difficulty of preventing human error, and improve the safety of related tests. Attached Figure Description
[0016] Figure 1 This is a schematic diagram of a method for real-time monitoring of the status of protection signals in a nuclear power plant. Detailed Implementation
[0017] The present invention will now be described in detail with reference to the accompanying drawings and specific embodiments.
[0018] like Figure 1 As shown, the steps of a method for real-time monitoring of the status of protection signals in a nuclear power plant are as follows: Step 1: Based on the required data volume, add a communication card to the non-secure platform; use the non-secure platform communication card, such as the IA platform FBM232, to establish communication between the non-secure platform and the secure platform, such as TRICONEX.
[0019] Step 2: Configure the communication protocol and data address, and debug to establish communication between the non-security platform and the security platform; establish communication points on the IA platform, establish a one-to-one correspondence between the storage location and the security platform points to be monitored, and create an FDSI (Field Device System Integrators) table.
[0020] Step 3: Create an interface module on the non-safety-level platform to receive data and perform threshold calculations; add a threshold calculation module on the non-safety-level platform, and set the new module to be exactly the same as the safe-level platform in terms of characteristic parameters such as maximum design range, unit, and rate of change.
[0021] Step 4: Create a logic calculation module and a quality level judgment module on the non-safety-grade platform to perform status judgment. The logic calculation module's logic thresholds for generating reactor protection and dedicated actions are close to those of the safety-grade platform, with a certain margin. The quality level judgment module will trigger display changes in the event of communication loss, over-range, or hardware failure to indicate that the corresponding point is abnormal. The over-range range configuration is consistent with that of the safety-grade platform to reflect the actual status of the quality level triggering at the safety-grade platform.
[0022] Step 5: Add a display module to the non-safety-grade platform for displaying the results of quality level and threshold comparisons. Design nested visual screens on the non-safety-grade platform. The first-level screen is a list of tests to be performed, indexed by system according to the work content. Clicking on a work object in the list jumps to the second-level screen. The second-level screen displays the test point information for a single channel. The bottom of the screen displays the test name; the screen links to relevant display modules showing the quality level and threshold trigger status of logic-related instruments. Each element in the second-level screen is defined by a relevant point on the non-safety-grade platform; clicking on the element displays the relevant configuration information. Create a screen on the non-safety-grade platform as the first-level screen; this screen arranges the tests to be performed, and each test element has a jump function; clicking on it links to the corresponding second-level screen.
[0023] Step Six: Click on an element in the secondary screen to display the corresponding configuration point. After confirmation, you can jump to the specific screen of the corresponding point on the non-security platform. You can call up the trend function on this screen to observe the real-time trend of signal quality or value.
[0024] Step 7: Before conducting a channel test, first enter the primary screen to select the test. After clicking to jump to the secondary screen, verify the quality of the relevant signals and the threshold triggering status. If red is found, verify whether the conditions for starting the test are met; otherwise, the anomaly must be eliminated before conducting the channel test.
Claims
1. A method for real-time monitoring of protection signal status in a nuclear power plant, characterized in that: The steps are as follows: Step 1: Add the communication card to the non-security platform; Step 2: Configure the communication protocol and data address, and debug to establish communication between the non-security platform and the security platform; Step 3: Create an interface module on the non-secure platform to receive data, and add a threshold calculation module on the non-secure platform to perform threshold calculation; Step 4: Create a logic calculation module on a non-security platform to perform logic calculations, and create a quality bit judgment module to perform status judgments; Step 5: Add a display module to the non-security platform to display the results of quality bit and threshold comparison.
2. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: The communication card mentioned is the IA platform FBM232.
3. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: The security-grade platform mentioned is TRICONEX.
4. The method for real-time monitoring of nuclear power plant protection signal status according to claim 2, characterized in that: Establish communication points on the IA platform, establish a one-to-one correspondence between the storage location and the security level platform points that need to be monitored, and create an FDSI table.
5. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: The threshold calculation module and the safety-level platform location are set identically in terms of maximum design range, unit, and rate of change characteristic parameters.
6. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: The logic calculation module is close to the logic threshold of the safety-grade platform for generating reactor protection and dedicated actions, leaving a certain margin.
7. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: The quality position judgment module will trigger a display change in the event of communication loss, over-range measurement, or hardware failure, to indicate that there is an anomaly at the corresponding position.
8. The method for real-time monitoring of nuclear power plant protection signal status according to claim 7, characterized in that: The overrange configuration is consistent with the safety-grade platform, reflecting the actual state of the safety-grade platform's point quality trigger.
9. The method for real-time monitoring of nuclear power plant protection signal status according to claim 1, characterized in that: Step five: Display the visual screen of the nested design of the relevant modules. The first layer screen is a list of tests to be performed. The system is indexed according to the work content. Clicking on the work object in the list will jump to the second layer screen. The second layer screen displays the test point information for a single channel. The test name is at the bottom of the screen. Each element in the second layer screen is defined by the relevant point of the non-safety-level platform. Clicking on the element will display the relevant configuration information. After confirmation, jump to the specific screen of the corresponding point of the non-safety-level platform and call up the trend function to observe the real-time trend of signal quality or value.
10. The method for real-time monitoring of nuclear power plant protection signal status according to claim 9, characterized in that: Step 5: Before conducting a channel test, first enter the first-level screen to select the test. After clicking to jump to the second-level screen, verify the quality of the relevant signals and the threshold triggering status. If red is found, verify whether the conditions for starting the test are met. Otherwise, the abnormality must be eliminated before conducting the channel test.