Nuclear power plant accident handling path feasibility judgment method, computer equipment and storage medium

Abstract

The invention particularly relates to a nuclear power plant accident handling path feasibility judgment method, computer equipment and a storage medium, and belongs to the technical field of nuclear power plant operation. The method comprises the steps of nuclear power plant state identification; nuclear power plant accident diagnosis and state tracking; evaluating the availability of nuclear power plant accident handling key equipment; evaluating the state of a nuclear power plant accident handling key system; nuclear power plant accident handling path feasibility judgment; and human-computer interface display. The computer equipment and the storage medium are used for implementing the steps of the method. According to the invention, the feasibility of the accident handling path is judged based on nuclear power plant equipment availability and system state evaluation, and when the nuclear power plant has an accident, an operator is helped to find the feasibility of the accident handling path in advance, so that a corresponding coping strategy is made in time, accident consequences are degraded to the maximum extent, and the safety of the nuclear power plant is improved.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power plant operation, and in particular to a feasibility judgment method for an accident handling path of a nuclear power plant, a computer device and a storage medium. Background Art

[0002] At the beginning, nuclear power plants generally adopted the event-oriented accident handling procedure (EOP), which is based on specific accident events, pre-sets a series of possible accident scenarios, and provides corresponding operation guidance and response measures for each scenario. With the development of nuclear power technology, people have realized that this event-oriented accident handling procedure based on the logic of single event handling cannot cope with multiple events or cumulative events, and has limitations. Faced with this situation, people began to actively carry out research on other accident handling procedures, among which the symptom-oriented accident handling procedure (SEOP) and the state-oriented accident handling procedure (SOP) are the main representatives.

[0003] The three accident handling procedures each have their own characteristics. The event-oriented accident handling procedure is a direct extension of the deterministic method in nuclear power plant design. It is efficient and accurate for specific design basis accidents, but its ability to deal with superimposed accidents is insufficient. The state-oriented accident handling procedure is an operation strategy designed based on the physical state of the reactor represented by six state functions. Its advantage is that it can deal with superimposed accidents, but the user experience is poor and the operation is complicated. The symptom-oriented accident handling procedure is based on the probabilistic method of accident analysis. The diagnosis direction is clear in the case of a single accident, and superimposed accidents can be effectively dealt with through symptom diagnosis. The procedure system has a clear idea, and it is highly executable and understandable. The symptom-oriented accident handling procedure has been widely recognized internationally and plays an increasingly important role in the process of establishing and improving the accident handling procedure system of nuclear power plants.

[0004] Once an accident occurs in a nuclear power plant, the operator will perform accident diagnosis, key safety function monitoring and accident handling operations in accordance with the predetermined accident handling procedures. However, if the equipment is unavailable or the system status is degraded during the accident handling process, the operator is often unable to respond in advance. It is necessary to wait until the specific steps in the procedures are executed before discovering that there is a problem with the required equipment or system, and then find a new accident handling path. This makes it difficult to achieve rapid and effective handling of nuclear power plant accidents and also poses a threat to the safety of nuclear power plants. Summary of the invention

[0005] Based on this, in order to solve the problem that during the accident handling process of a nuclear power plant, the operator cannot discover the feasibility of the accident handling path in advance, and once the accident handling path is not feasible, a new accident handling path needs to be found again, resulting in the inability to quickly and effectively handle the nuclear power plant accident, posing a threat to the safety of the nuclear power plant, the present invention provides a feasibility judgment method for an accident handling path of a nuclear power plant, a computer device and a storage medium. The method judges the feasibility of the accident handling path based on the availability of nuclear power plant equipment and the system status evaluation. When an accident occurs in a nuclear power plant, the method helps the operator discover the feasibility of the accident handling path in advance, and then make corresponding response strategies in time, so as to minimize the consequences of the accident and improve the safety of the nuclear power plant.

[0006] In order to solve the above problems, the present invention provides a method for determining the feasibility of a nuclear power plant accident handling path, comprising the following steps:

[0007] Step 1: Identification of nuclear power plant status;

[0008] Step 2: Nuclear power plant accident diagnosis and status tracking;

[0009] Step 3: Availability assessment of key equipment for nuclear power plant accident handling;

[0010] Step 4: Status assessment of key systems for nuclear power plant accident handling;

[0011] Step 5: Feasibility assessment of the nuclear power plant accident handling path;

[0012] Step 6: Human-machine interface display.

[0013] As one of the feasible methods, step 1, nuclear power plant status identification, includes the following steps:

[0014] Step 101, collecting a small amount of key parameters of the DCS system or simulator of the nuclear power plant; the collected key parameters include nuclear power, primary circuit coolant loading, primary circuit pressure, primary circuit average temperature and primary circuit boron concentration;

[0015] Step 102: Compare the collected key parameters with preset key parameters to determine the operation mode of the nuclear power plant.

[0016] As one of the feasible methods, step 1, nuclear power plant status identification, includes the following steps:

[0017] Step 101, collecting key parameters of a nuclear power plant simulator; the collected key parameters include nuclear power, primary circuit coolant loading, primary circuit pressure, primary circuit average temperature and primary circuit boron concentration;

[0018] Step 102: Compare the collected key parameters with the preset key parameters in each operation mode of the nuclear power plant to determine whether the nuclear power plant is in a power operation mode.

[0019] As one of the feasible methods, step 2, nuclear power plant accident diagnosis and status tracking, includes the following steps:

[0020] Step 201, collecting characteristic parameters of a DCS system or simulator of a nuclear power plant;

[0021] Step 202: compare the collected characteristic parameters with the preset accident characteristic parameters under the operation mode of the nuclear power plant, and diagnose the corresponding accident after a preset logical judgment;

[0022] Step 203: In the subsequent accident handling process, the cyclic diagnosis of accidents is realized by monitoring the key safety functions of the unit, so as to timely discover more serious superimposed accidents or functional degradation.

[0023] As one of the feasible methods, step three, the availability assessment of key equipment for nuclear power plant accident handling, includes the following steps:

[0024] Step 301: sort out the key equipment for accident handling according to the accident handling path description in the accident handling procedure;

[0025] Step 302: Collect relevant data of key equipment for accident handling on the DCS system or simulator of the nuclear power plant; the relevant data of key equipment for accident handling include power supply status, circuit breaker / bus status, current / voltage signal, temperature signal, pressure signal, vibration signal, flow signal, isolation data and maintenance data;

[0026] Step 303: Based on the associated data of the key accident handling equipment, a comprehensive evaluation is performed on the availability of the key accident handling equipment, and an availability evaluation result of the key accident handling equipment is given as available or unavailable.

[0027] As one of the feasible methods, step 4, the status assessment of key systems for nuclear power plant accident handling, includes the following steps:

[0028] Step 401, collecting status parameters of key accident handling systems on a nuclear power plant DCS system or simulator;

[0029] Step 402: Based on the status parameters of the critical accident handling system and the availability assessment results of the critical accident handling equipment, the status of the critical accident handling system is assessed in accordance with the functions to be achieved by the critical accident handling system, and the critical accident handling system status assessment results are given as normal, partially degraded, severely degraded or failed.

[0030] As one of the feasible methods, step 5, feasibility determination of nuclear power plant accident handling path, includes the following steps:

[0031] Step 501: pre-judge the feasibility of the accident handling path according to the availability assessment results of the key accident handling equipment and the status assessment results of the key accident handling system, combined with the logical judgment of the preset accident handling procedures;

[0032] Step 502: Track the status of the unit in real time and adjust the feasibility judgment result of the accident handling path in time.

[0033] As one of the feasible methods, in step six, a brief description of the accident handling path, a detailed description of the accident handling path and the availability assessment results of the key equipment for accident handling are displayed on the human-machine interface, and the feasibility judgment results of the accident handling path and the availability assessment results of the key equipment for accident handling are displayed in different colors.

[0034] In order to solve the above problems, the present invention also provides a computer device, including a memory and a processor, wherein the memory stores computer-readable instructions, and when the processor executes the computer-readable instructions, the steps of the feasibility judgment method of the above-mentioned nuclear power plant accident handling path are implemented.

[0035] In order to solve the above problems, the present invention also provides a computer-readable storage medium, on which computer-readable instructions are stored. When the computer-readable instructions are executed, the steps of the feasibility judgment method of the above-mentioned nuclear power plant accident handling path are implemented.

[0036] Beneficial technical effects of the present invention:

[0037] The feasibility judgment method, computer equipment and storage medium of the nuclear power plant accident handling path of the present invention judge the feasibility of the accident handling path through the availability evaluation of key accident handling equipment and the status evaluation of key accident handling systems; when an accident occurs in a nuclear power plant and the operating personnel execute the accident handling procedures, the feasibility of the accident handling path is pre-judged, so that the operating personnel know the feasibility judgment result of the accident handling path in advance, help the operating personnel to correctly select a feasible accident handling path, respond to faulty equipment or degraded systems in advance, minimize the consequences of the accident, and improve the efficiency and safety of nuclear power plant accident handling. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] Figure 1 A flowchart of an embodiment of a method for determining feasibility of a nuclear power plant accident handling path according to the present invention;

[0039] Figure 2 A flow chart of a method for determining the feasibility of a core cooling insufficiency accident treatment path;

[0040] Figure 3 Schematic diagram of the availability assessment results of key equipment for handling core cooling deficiency accidents;

[0041] Figure 4 A schematic diagram briefly describes the treatment path for the core cooling deficiency accident;

[0042] Figure 5 A schematic diagram for describing in detail the treatment path for the core cooling deficiency accident;

[0043] Figure 6 This is a schematic diagram of the feasibility judgment results of the core cooling insufficient accident handling path. DETAILED DESCRIPTION

[0044] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application.

[0045] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.

[0046] The terms "comprises," "comprising," or any other variations thereof, are intended to cover a non-exclusive inclusion of the elements listed and may also include additional elements not expressly listed.

[0047] See also Figure 1 The present invention provides a method for determining the feasibility of a nuclear power plant accident handling path, comprising the following steps:

[0048] Step 1: Identification of nuclear power plant status;

[0049] Step 2: Nuclear power plant accident diagnosis and status tracking;

[0050] Step 3: Availability assessment of key equipment for nuclear power plant accident handling;

[0051] Step 4: Status assessment of key systems for nuclear power plant accident handling;

[0052] Step 5: Feasibility assessment of the nuclear power plant accident handling path;

[0053] Step 6: Human-machine interface display.

[0054] As one of the feasible methods, step 1, nuclear power plant status identification, includes the following steps:

[0055] Step 101, collecting key parameters of the DCS system or simulator of the nuclear power plant; the collected key parameters include nuclear power, primary circuit coolant loading, primary circuit pressure, primary circuit average temperature and primary circuit boron concentration;

[0056] Step 102: Compare the collected key parameters with the preset key parameters in each operation mode of the nuclear power plant to determine the operation mode of the nuclear power plant.

[0057] Common operating modes of nuclear power plants include but are not limited to power operation mode, hot standby mode, cold shutdown mode, refueling / maintenance mode, and startup / shutdown transition mode. The operating mode of a nuclear power plant can be judged by changes in key parameters, especially the combination of nuclear power, primary coolant loading, primary pressure, primary average temperature, and primary boron concentration. The corresponding nuclear power, primary coolant loading, primary pressure, primary average temperature, and primary boron concentration are preset in each operating mode. By collecting the key parameters of the nuclear power plant DCS system or simulator and comparing the collected key parameters with the preset key parameters in each operating mode of the nuclear power plant, the operating mode of the nuclear power plant can be judged, providing prerequisites for subsequent accident diagnosis and the correct use of accident handling procedures.

[0058] As one of the feasible methods, step 2, nuclear power plant accident diagnosis and status tracking, includes the following steps:

[0059] Step 201, collecting characteristic parameters of a DCS system or simulator of a nuclear power plant;

[0060] Step 202: compare the collected characteristic parameters with the preset accident characteristic parameters under the operation mode of the nuclear power plant, and diagnose the corresponding accident after a preset logical judgment;

[0061] Step 203: In the subsequent accident handling process, the cyclic diagnosis of accidents is realized by monitoring the key safety functions of the unit, so as to timely discover more serious superimposed accidents or functional degradation.

[0062] As one of the feasible methods, step three, the availability assessment of key equipment for nuclear power plant accident handling, includes the following steps:

[0063] Step 301: sort out the key equipment for accident handling according to the accident handling path description in the accident handling procedure;

[0064] Step 302: Collect relevant data of key equipment for accident handling on the DCS system or simulator of the nuclear power plant; the relevant data of key equipment for accident handling include power supply status, circuit breaker / bus status, current / voltage signal, temperature signal, pressure signal, vibration signal, flow signal, isolation data and maintenance data;

[0065] Step 303: Based on the associated data of the key accident handling equipment, a comprehensive evaluation is performed on the availability of the key accident handling equipment, and an availability evaluation result of the key accident handling equipment is given as available or unavailable.

[0066] As one of the feasible methods, step 4, the status assessment of key systems for nuclear power plant accident handling, includes the following steps:

[0067] Step 401, collecting status parameters of key accident handling systems on a nuclear power plant DCS system or simulator;

[0068] Step 402: According to the status parameters of the critical accident handling system and the availability evaluation results of the critical accident handling equipment, the status of the critical accident handling system is evaluated according to the functions to be realized by the critical accident handling system, and the status evaluation results of the critical accident handling system are given as normal, partially degraded, severely degraded or failed;

[0069] The key systems for accident handling include special equipment, heat sinks, power supplies and instrument compressed air used in the accident handling process, such as the safety injection system, containment spray system, instrument compressed air system, equipment cooling water system, important plant water system, auxiliary water supply system, turbine bypass discharge system, atmosphere monitoring system in containment, spent water pool system and power supply system.

[0070] As one of the feasible methods, step 5, feasibility determination of nuclear power plant accident handling path, includes the following steps:

[0071] Step 501: pre-judge the feasibility of the accident handling path according to the availability assessment results of the key accident handling equipment and the status assessment results of the key accident handling system, combined with the logical judgment of the preset accident handling procedures;

[0072] Step 502: Track the status of the unit in real time and adjust the feasibility judgment result of the accident handling path in time.

[0073] According to the results of key equipment availability assessment and key system status assessment, combined with the logical judgment of the preset accident handling procedures, the feasibility judgment results of the accident handling path can be obtained in advance when the accident handling procedures have not yet been executed to a certain step, so as to achieve preliminary analysis and judgment of the accident handling path, so as to make corresponding response strategies in time, such as using alternative accident handling paths and maintenance equipment to minimize the consequences of the accident, thereby improving the safety of nuclear power plants.

[0074] As one of the feasible ways, in order to facilitate operating personnel to timely understand the accident handling status of the nuclear power plant, a brief description of the accident handling path, a detailed description of the accident handling path, and the availability assessment results of key accident handling equipment are displayed on the human-machine interface, and the feasibility judgment results of the accident handling path and the availability assessment results of key accident handling equipment are displayed in different colors.

[0075] The technical solution of the present invention is clearly and completely described below in conjunction with the accompanying drawings and specific embodiments.

[0076] Example 1

[0077] Taking the core cooling deficiency accident in a domestic nuclear power plant as an example, the feasibility judgment method of the nuclear power plant accident handling path of the present invention is further described in detail.

[0078] The present embodiment provides a method for determining the feasibility of an accident handling path in a nuclear power plant. By collecting real-time data from a nuclear power plant simulator, the accident type is accurately identified and diagnosed. Based on the availability assessment results of key accident handling equipment and key system status assessment results and a preset accident handling path logic, the feasibility of the accident handling path is determined and processed.

[0079] The feasibility determination method of the nuclear power plant accident handling path described in this embodiment includes the following steps:

[0080] Step 1: Identification of nuclear power plant status;

[0081] Step 2: Nuclear power plant accident diagnosis and status tracking;

[0082] Step 3: Availability assessment of key equipment for nuclear power plant accident handling;

[0083] Step 4: Status assessment of key systems for nuclear power plant accident handling;

[0084] Step 5: Feasibility assessment of the nuclear power plant accident handling path;

[0085] Step 6: Human-machine interface display.

[0086] In this embodiment, step 1, nuclear power plant status identification, includes the following steps:

[0087] Step 101, collecting key parameters of a nuclear power plant simulator; the collected key parameters include nuclear power, primary circuit coolant loading, primary circuit pressure, primary circuit average temperature and primary circuit boron concentration;

[0088] Step 102: Compare the collected key parameters with the preset key parameters in each operation mode of the nuclear power plant to determine whether the nuclear power plant is in a power operation mode.

[0089] In this embodiment, step 2, nuclear power plant accident diagnosis and status tracking, includes the following steps:

[0090] Step 201, inserting a core cooling insufficient accident sequence into a nuclear power plant simulator;

[0091] Step 202, collecting characteristic parameters of a nuclear power plant simulator;

[0092] Step 203: compare the collected characteristic parameters with the accident characteristic parameters preset in the operation mode of the nuclear power plant, and diagnose the existence of the core cooling deficiency accident through a preset logical judgment;

[0093] Step 204: During the subsequent accident handling process, the critical safety functions of the unit are monitored to achieve cyclic diagnosis of accidents, so as to timely discover more serious superimposed accidents or functional degradation.

[0094] See also Figure 3 In this embodiment, step three, assessing the availability of key equipment for handling nuclear power plant accidents, includes the following steps:

[0095] Step 301, sort out the key equipment for handling the insufficient core cooling accident according to the description of the insufficient core cooling accident handling path in the insufficient core cooling accident handling procedure; the key equipment for handling the insufficient core cooling accident includes a feed water tank, a feed water pump, a main pump, an electric heater, a pressurizer and a high-pressure injection pump;

[0096] Step 302, collecting the associated data of the key equipment for handling the accident of insufficient core cooling on the nuclear power plant simulator; the associated data of the key equipment for handling the accident of insufficient core cooling includes power supply status, circuit breaker / bus status, current / voltage signal, temperature signal, pressure signal, vibration signal, flow signal, isolation data and maintenance data;

[0097] Step 303: comprehensively evaluate the availability of the key equipment for handling the core cooling shortage accident according to the associated data of the key equipment for handling the core cooling shortage accident, and provide an availability evaluation result of the key equipment for handling the core cooling shortage accident as available or unavailable;

[0098] Among them, the availability assessment results of the water supply tank, water supply pump, main pump, electric heater and voltage stabilizer are all available, and the availability assessment result of the high-pressure injection pump is unavailable.

[0099] In this embodiment, by monitoring the voltage at the motor of the high-pressure injection pump to be 0, it is evaluated that the availability evaluation result of the high-pressure injection pump is unavailable.

[0100] In this embodiment, step 4, assessing the status of key systems for handling nuclear power plant accidents, includes the following steps:

[0101] Step 401, collecting state parameters of key systems for handling insufficient core cooling accidents on a nuclear power plant simulator; the key systems for handling insufficient core cooling accidents include a safety injection system during handling insufficient core cooling accidents;

[0102] Step 402: According to the state parameters of the safety injection system and the evaluation result that the high-pressure safety injection pump is unavailable, the state of the safety injection system is evaluated as partially degraded according to the functions to be achieved by the safety injection system.

[0103] In this embodiment, step five, feasibility determination of the nuclear power plant accident handling path, includes the following steps:

[0104] Step 501: According to the evaluation result of the high-pressure injection pump being unavailable and the evaluation result of the partial degradation of the safety injection system, combined with the logic of the preset core cooling insufficient accident handling procedure, the feasibility of the core cooling insufficient accident handling path is pre-determined;

[0105] Step 502: Track the unit status in real time and adjust the feasibility judgment result of the core cooling insufficient accident handling path in a timely manner.

[0106] According to the availability assessment results of key equipment for handling insufficient core cooling accidents and the status assessment results of key systems for handling insufficient core cooling accidents, combined with the logical judgment of the preset insufficient core cooling accident handling procedures, the feasibility judgment results of the insufficient core cooling accident handling path can be obtained in advance before the operating personnel have executed a certain step of the insufficient core cooling accident handling procedure, so as to achieve pre-analysis and judgment of the insufficient core cooling accident handling path, so as to make corresponding response strategies in time, such as using the spare insufficient core cooling accident handling path and repairing the high-pressure injection pump, so as to minimize the consequences of the insufficient core cooling accident, thereby improving the safety of the nuclear power plant.

[0107] like Figure 2 When a core cooling shortage accident occurs in a nuclear power plant under power operation mode, there are three accident handling paths:

[0108] The first accident handling path is: establish high-pressure injection flow and inject coolant into the core;

[0109] The second accident handling path is: the secondary side of the intact steam generator is depressurized under controlled conditions, and the medium-pressure injection pump and low-pressure injection pump are used to inject coolant into the core;

[0110] The third accident handling path is to start the main pump and establish forced two-phase flow to temporarily cool the core.

[0111] The feasibility of each accident handling path is determined by the availability of key equipment and the status of key systems on the accident handling path. For example, the first accident handling path is determined by the availability of three high-pressure injection pumps and related valves and whether there is high-pressure injection flow. Since the judgment results of steps three and four show that the first accident handling path is not feasible, the operating personnel can directly use the second or third accident handling path to handle the accident, thereby directly skipping the execution of the first accident handling path to prevent the unit from deteriorating to a more serious state.

[0112] See also Figure 3-6 In this embodiment, in step six, in order to facilitate the operating personnel to timely understand the status of the core cooling shortage accident processing, a brief description of the core cooling shortage accident processing path, a detailed description of the core cooling shortage accident processing path and the availability assessment results of the key equipment for the core cooling shortage accident processing are displayed on the human-machine interface, and the feasibility judgment results of the core cooling shortage accident processing path and the availability assessment results of the key equipment for the core cooling shortage accident processing are displayed in different colors.

[0113] As an implementation of the above method, the present invention provides an embodiment of a computer device, and the embodiment of the computer device corresponds to the embodiment of the feasibility judgment method of the nuclear power plant accident handling path.

[0114] The computer device described in this embodiment includes a memory, a processor and a network interface that are interconnected and communicated through a system bus. It should be noted that the figure only shows a computer device with a memory, a processor and a network interface, but it should be understood that it is not required to implement all the components shown, and more or fewer components can be implemented instead. Among them, those skilled in the art can understand that the computer device here is a device that can automatically perform numerical calculations and / or information processing according to pre-set or stored instructions, and its hardware includes but is not limited to a microprocessor, an application-specific integrated circuit, a programmable gate array, a digital processor, an embedded device, etc.

[0115] The computer device may be a computing device such as a desktop computer, a notebook, a PDA, a cloud server, etc. The computer device may interact with a user through a keyboard, a mouse, a remote controller, a touch pad, or a voice control device.

[0116] The memory includes at least one type of readable storage medium, and the readable storage medium includes flash memory, hard disk, multimedia card, card-type memory, random access memory, static random access memory, read-only memory, electrically erasable programmable read-only memory, programmable read-only memory, magnetic memory, disk, optical disk, etc. In some embodiments, the memory may be an internal storage unit of the computer device, such as a hard disk or memory of the computer device. In other embodiments, the memory may also be an external storage device of the computer device, such as a plug-in hard disk, smart memory card, secure digital card, flash memory card, etc. equipped on the computer device. Of course, the memory may also include both the internal storage unit of the computer device and its external storage device. In this embodiment, the memory is generally used to store the operating system and various application software installed on the computer device, such as the computer-readable instructions of the feasibility judgment method of the above-mentioned nuclear power plant accident handling path. In addition, the memory may also be used to temporarily store various types of data that have been output or are to be output.

[0117] In some embodiments, the processor may be a central processing unit, a controller, a microcontroller, a microprocessor, or other data processing chip. The processor is generally used to control the overall operation of the computer device. In this embodiment, the processor is used to run the computer-readable instructions stored in the memory or process data, such as running the computer-readable instructions of the feasibility determination method for the above-mentioned nuclear power plant accident handling path.

[0118] The network interface may include a wireless network interface or a wired network interface, which is generally used to establish a communication connection between the computer device and other electronic devices.

[0119] As an implementation of the above method, the present invention provides an embodiment of a computer-readable storage medium, and the embodiment of the computer-readable storage medium corresponds to the embodiment of the feasibility judgment method of the above nuclear power plant accident handling path.

[0120] The computer-readable storage medium described in this embodiment stores computer-readable instructions, and the computer-readable instructions can be executed by at least one processor to enable the at least one processor to perform the steps of the feasibility judgment method for the nuclear power plant accident handling path as described above.

[0121] The above-mentioned embodiments only express several implementation methods of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the scope of protection of the present invention. Therefore, the scope of protection of the patent of the present invention shall be subject to the attached claims.

Claims

1. A method for determining the feasibility of a nuclear power plant accident handling path, characterized in that: The steps include: Step 1: Identification of nuclear power plant status; Step 2: Nuclear power plant accident diagnosis and status tracking; Step 3: Availability assessment of key equipment for nuclear power plant accident handling; Step 4: Status assessment of key systems for nuclear power plant accident handling; Step 5: Feasibility assessment of the nuclear power plant accident handling path; Step 6: Human-machine interface display.

2. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 1, characterized in that: Step 1, nuclear power plant status identification, includes the following steps: Step 101, collecting key parameters of a DCS system or simulator of a nuclear power plant; Step 102: Compare the collected key parameters with preset key parameters to determine the operation mode of the nuclear power plant.

3. The feasibility determination method for a nuclear power plant accident handling path according to claim 2, characterized in that: Step 2, nuclear power plant accident diagnosis and status tracking, includes the following steps: Step 201, collecting characteristic parameters of a DCS system or simulator of a nuclear power plant; Step 202: compare the collected characteristic parameters with the preset accident characteristic parameters under the operation mode of the nuclear power plant, and diagnose the corresponding accident after a preset logical judgment; Step 203: In the subsequent accident handling process, the cyclic diagnosis of accidents is realized by monitoring the key safety functions of the unit, so as to timely discover more serious superimposed accidents or functional degradation.

4. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 3, characterized in that: Step 3: Availability assessment of key equipment for nuclear power plant accident handling, including the following steps: Step 301: sort out the key equipment for accident handling according to the accident handling path description in the accident handling procedure; Step 302: Collect relevant data of key accident handling equipment on the DCS system or simulator of the nuclear power plant; Step 303: Based on the associated data of the key accident handling equipment, a comprehensive evaluation is performed on the availability of the key accident handling equipment, and an availability evaluation result of the key accident handling equipment is given as available or unavailable.

5. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 4, characterized in that: In step 101, the key parameters collected include nuclear power, primary circuit coolant loading, primary circuit pressure, primary circuit average temperature and primary circuit boron concentration; in step 302, the associated data of key accident handling equipment include power status, circuit breaker / bus status, current / voltage signal, temperature signal, pressure signal, vibration signal, flow signal, isolation data and maintenance data.

6. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 4, characterized in that: Step 4: Assessment of the status of key systems for nuclear power plant accident handling, including the following steps: Step 401, collecting status parameters of key accident handling systems on a nuclear power plant DCS system or simulator; Step 402: Based on the status parameters of the critical accident handling system and the availability assessment results of the critical accident handling equipment, the status of the critical accident handling system is assessed in accordance with the functions to be achieved by the critical accident handling system, and the critical accident handling system status assessment results are given as normal, partially degraded, severely degraded or failed.

7. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 6, characterized in that: Step 5: Feasibility assessment of the nuclear power plant accident handling path, including the following steps: Step 501: pre-judge the feasibility of the accident handling path according to the availability assessment results of the key accident handling equipment and the status assessment results of the key accident handling system, combined with the logical judgment of the preset accident handling procedures; Step 502: Track the status of the unit in real time and adjust the feasibility judgment result of the accident handling path in time.

8. The method for determining the feasibility of a nuclear power plant accident handling path according to claim 7, characterized in that: In step six, a brief description of the accident handling path, a detailed description of the accident handling path, and an evaluation result of the availability of key equipment for accident handling are displayed on the human-machine interface, and the feasibility judgment result of the accident handling path and the evaluation result of the availability of key equipment for accident handling are displayed in different colors.

9. A computer device comprising a memory and a processor, wherein the memory stores computer-readable instructions, characterized in that: When the processor executes the computer-readable instructions, the processor implements the steps of the method for determining the feasibility of a nuclear power plant accident handling path as described in any one of claims 1 to 8.

10. A computer-readable storage medium having computer-readable instructions stored thereon, characterized in that: When the computer-readable instructions are executed, the steps of the method for determining the feasibility of a nuclear power plant accident handling path as described in any one of claims 1 to 8 are implemented.

Images