Primary circuit pressure-temperature map switching method, control device, and storage medium

Abstract

The application relates to a primary loop pressure-temperature diagram switching method, a control device and a storage medium, which method comprises the following steps: S10, acquiring key parameters; wherein the key parameters comprise state function parameters capable of representing physical states of a unit, device and system state parameters capable of representing running states of primary loop devices and systems, protection signals capable of representing reactor states and alarm signals capable of representing alarm information generated by the devices and systems; S20, diagnosing the states of the unit according to the key parameters, and generating a switching signal according to a diagnosis result; and S30, switching the primary loop pressure-temperature diagram according to the switching signal, and returning to the S10. The application can automatically switch the primary loop pressure-temperature diagram based on the current states of the unit, and can effectively avoid frequent manual switching operations of an operator during the use of the primary loop pressure-temperature diagram.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant equipment control technology, and in particular to a method for switching primary loop pressure-temperature diagrams, control equipment, and storage medium. Background Technology

[0002] To ensure the safe operation of nuclear power plants, pressure and temperature diagrams of the primary loop under different operating conditions (including fault condition diagrams, accident condition diagrams, natural circulation condition diagrams, and normal operation condition diagrams) are used to represent the operating status of the nuclear power plant in real time. This helps staff track the reactor status in real time and assists operators in continuously tracking and controlling the unit status.

[0003] While some nuclear power plants have developed simple judgment logic for selecting the appropriate primary circuit pressure-temperature diagram in related technologies, these solutions generally suffer from the following drawbacks: low level of intelligence; at the execution level, operators need to make accurate diagnoses of the unit's current operating conditions based on their own experience and the unit's physical state parameters; and during accident handling, frequent manual switching of the primary circuit pressure-temperature diagram is required in conjunction with the status of the ongoing accident operation procedures and protection signals, resulting in a heavy workload for operators, a high risk of human error, and relatively simple and crude judgment logic that cannot be integrated with the nuclear power plant's digital instrumentation and control system for automatic diagnosis, posing a threat to the safe operation of the unit. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to provide a method for switching a primary circuit pressure-temperature diagram, a control device, and a storage medium.

[0005] The technical solution adopted by this invention to solve its technical problem is: constructing a primary loop pressure-temperature diagram switching method, including the following steps: S10. Obtain key parameters; wherein, the key parameters include status function parameters that can represent the physical state of the unit, equipment and system status parameters that can represent the operating state of the primary loop equipment and system, protection signals that can represent the reactor state, and alarm signals that can represent the alarm information generated by the equipment and system. S20. Diagnose the status of the unit based on the key parameters and generate a switching signal based on the diagnosis results; S30. Switch the primary circuit pressure-temperature diagram according to the switching signal and return to S10.

[0006] Preferably, in step S20, the step of diagnosing the status of the unit based on the key parameters includes: Based on the established diagnostic rules and the key parameters, a variety of preset degradation requirements are diagnosed sequentially, and when it is determined that a certain degradation requirement needs to be downgraded, a diagnostic result is generated based on that certain degradation requirement.

[0007] Preferably, in step S20, diagnosing the unit's status based on the key parameters includes: S201. Perform a primary loop state diagnosis to determine whether the primary loop state needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S202. S202. Perform a primary loop water capacity diagnosis to determine whether the primary loop water capacity needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S203. S203. Determine whether the saturation margin of the primary coolant circuit is greater than the first set margin value. If yes, execute S204; otherwise, execute S207. S204. Perform a primary loop subcooling diagnosis to determine whether the primary loop subcooling needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S205. S205. Perform nuclear power diagnosis to determine whether nuclear power needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S206. S206. Perform waste heat extraction function diagnosis to determine whether waste heat extraction needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S208. S207. Perform waste heat export function diagnosis. If it is determined that the waste heat export needs to be downgraded, the diagnosis ends. If it is determined that the waste heat export does not need to be downgraded, perform the nuclear power diagnosis. If the nuclear power needs to be downgraded, the diagnosis ends. If the nuclear power does not need to be downgraded, proceed to S208. S208. Perform containment status diagnosis to determine whether the containment status needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S209. S209. Perform a second-loop status diagnosis to determine whether the second loop needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S2010. S2010. Perform status function diagnosis to determine whether the status function needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S2011. S2011. Perform operating condition diagnosis to determine the current operating condition, and the diagnosis ends; wherein, the current operating condition includes fault operating condition, normal operating condition and natural cycle operating condition.

[0008] Preferably, in S10, the state function parameters include primary coolant saturation margin, pressure vessel water level, steam generator pressure, steam generator liquid level, containment pressure, reactor coolant system loop liquid level, primary loop leakage rate, containment dose rate, core outlet temperature, intermediate range power, emergency shutdown time, and primary loop pressure. The equipment and system status parameters include primary loop status parameters, emergency boronizing system status parameters, steam generator status parameters, reactor boron and water supply system status parameters, reactor coolant system main pump status parameters, equipment cooling water system status parameters, and safety injection system status parameters. The protection signals include a cold overpressure protection signal, a waste heat discharge permission signal, a safety injection trigger signal, and a safety injection switching signal. The alarm information includes alarm information from the emergency power distribution system, high temperature alarm information from the main steam system, and feedback information from the radiation monitoring system.

[0009] Preferably, in S201, the first-loop status diagnosis includes: determining whether the first-loop is in a closed state based on the first-loop status parameters and determining whether the emergency power distribution system is in an emergency alarm state based on the emergency power distribution system alarm information. If the first-loop is not in a closed state or the emergency power distribution system is in an emergency alarm state, then the first-loop is determined to require degradation; otherwise, the first-loop is determined not to require degradation.

[0010] Preferably, in S202, the primary loop water level diagnosis includes: S2021. Determine whether at least one main pump is running based on the status parameters of the reactor coolant system main pump. If so, determine that the primary loop water loading does not need to be downgraded; otherwise, proceed to S2022. S2022. Determine whether the saturation margin of the primary coolant is less than the fourth set margin value and whether the water level of the pressure vessel is less than the set water level value. If either criterion is met, it is determined that the water volume of the primary coolant needs to be downgraded. If neither criterion is met, it is determined that the water volume of the primary coolant does not need to be downgraded.

[0011] Preferably, in S204, the primary loop subcooling diagnosis includes: S2041. Determine whether the cold overpressure protection signal is effective. If yes, execute S2044; otherwise, execute S2042. S2042. Determine whether the waste heat output permission connection signal is effective. If yes, execute S2043; otherwise, execute S2045. S2043. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the status parameters of the safety injection system. If so, execute S2044. S2044. Determine whether the pressure of the primary circuit is greater than the first set pressure value. If so, determine that the subcooling of the primary circuit needs to be downgraded; otherwise, determine that the subcooling of the primary circuit does not need to be downgraded. S2045. Determine whether at least one main pump is running based on the status parameters of the reactor coolant system main pump. If yes, proceed to S2046; otherwise, proceed to S2047. S2046. Determine whether the saturation margin of the primary coolant circuit is greater than the second set margin value. If so, determine that the primary circuit subcooling needs to be downgraded; otherwise, determine that the primary circuit subcooling does not need to be downgraded. S2047. Determine whether the saturation margin of the primary coolant circuit is greater than the third set margin value. If so, determine that the primary circuit subcooling needs to be downgraded; otherwise, determine that the primary circuit subcooling does not need to be downgraded. Wherein, the third set margin value is less than the second set margin value.

[0012] Preferably, in S204, the second set margin value is equal to 180°C; and / or the third set margin value is equal to 140°C; and / or the first set pressure value is equal to 5 MPa.G.

[0013] Preferably, in S205, the nuclear power diagnosis includes: S2051. Determine whether the intermediate range power is less than the first set flux. If so, determine that the nuclear power does not need to be downgraded. Otherwise, execute S2052. S2052. Determine whether the emergency shutdown time is less than the first set time. If so, execute S2053; otherwise, determine that the nuclear power needs to be downgraded. S2053. Determine whether the intermediate range power is less than the second set flux. If so, determine that the core power does not need to be downgraded; otherwise, determine that the core power needs to be downgraded.

[0014] Preferably, in S205, the first set flux is equal to ; and / or the first set time is equal to 20 minutes; and / or the second set flux is equal to 3%PN.

[0015] Preferably, in step 206, the waste heat removal function diagnosis includes: S2061. Determine whether there is at least one safety injection subsystem working in waste heat export mode based on the safety injection system status parameters. If so, determine that waste heat export does not need to be downgraded; otherwise, execute S2062. S2062. Determine whether the waste heat output permission connection signal is effective. If yes, execute S2063; otherwise, execute S2069. S2063. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the status parameters of the safety injection system. If yes, execute S2064; otherwise, execute S2069. S2064. Determine whether there is at least one unisolated steam generator with a pressure lower than the second set pressure value based on the steam generator status parameters and the steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded. S2065. Based on the steam generator status parameters and the steam generator liquid level, determine whether there is at least one unisolated steam generator with a liquid level greater than the first set liquid level. If so, execute S2066; otherwise, determine that the waste heat removal function needs to be downgraded. S2066. Determine whether the core outlet temperature is lower than the fourth set temperature. If yes, execute S2067. Otherwise, determine that the residual heat removal function needs to be downgraded. S2067. Determine whether the core outlet temperature is lower than the fifth set temperature. If so, determine that the residual heat removal function does not need to be downgraded; otherwise, execute S2068. S2068. Determine whether a main pump is running based on the status parameters of the reactor coolant system main pump. If so, determine that the waste heat removal function needs to be downgraded; otherwise, determine that the waste heat removal function does not need to be downgraded. S2069. Determine whether there is at least one unisolated steam generator with a pressure lower than the third set pressure value based on the steam generator status parameters and the steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded.

[0016] Preferably, in step 206, the second set pressure value is equal to 1.4 MPa.G; and / or the third set pressure value is equal to 8.95 MPa.G; and / or the first set liquid level is equal to 2.59 meters; and / or the fourth set temperature is equal to 335°C; and / or the fifth set temperature is equal to 320°C.

[0017] Preferably, in step 208, the containment condition diagnosis includes: Determine whether the dose rate inside the containment is less than the set dose rate. If so, determine that the containment status does not need to be downgraded; otherwise, determine that the containment status needs to be downgraded.

[0018] Preferably, in S209, the second-loop status diagnosis includes: Based on the feedback information from the radiation monitoring system, it is determined whether at least one steam generator has triggered a radiation alarm. If so, the secondary loop status needs to be downgraded; otherwise, the secondary loop status does not need to be downgraded.

[0019] Preferably, in S2010, the status function diagnosis includes: SS101: Determine whether at least one steam generator is unavailable based on the steam generator status parameters. If so, determine that the status function needs to be downgraded; otherwise, execute SS102. SS102. Determine whether the pressure difference between the unisolated steam generators is less than the fourth set pressure value based on the steam generator status and the steam generator pressure. If so, execute SS103; otherwise, determine that the status function needs to be downgraded. SS103. Determine whether at least one valve in the main steam system has a high temperature alarm based on the high temperature alarm information of the main steam system. If so, determine that the status function needs to be downgraded; otherwise, execute SS104. SS104. Determine whether the saturation margin of the primary coolant circuit is greater than the first set margin value. If so, execute SS105; otherwise, determine that the status function needs to be downgraded. SS105. Determine whether the injection switching signal is effective. If yes, execute SS106; otherwise, execute SS1010. SS106. Determine whether the injection trigger signal is effective. If yes, execute SS107; otherwise, determine that the status function needs to be downgraded. SS107. Determine whether the reactor coolant system loop liquid level is greater than the second set liquid level. If so, execute SS108; otherwise, determine that the status function needs to be downgraded. SS108. Determine whether the leakage rate of the primary loop is greater than the set leakage rate. If so, determine that the status function needs to be downgraded; otherwise, execute SS109. SS109. Determine whether the containment pressure is less than the fifth preset pressure value. If so, the determination state function does not need to be downgraded; otherwise, the determination state function needs to be downgraded. SS1010: Determine if the voltage regulator pressure is greater than the sixth set pressure value. If so, determine if the status function needs to be downgraded; otherwise, execute SS108.

[0020] Preferably, in S2010, the fourth set pressure value is equal to 1 MPa; and / or the second set liquid level is equal to 0.45 meters; and / or the fifth set pressure value is equal to 0.12 MPa.a; and / or the sixth set pressure value is equal to 11.4 MPa.G.

[0021] Preferably, in S2011, the operating condition diagnosis includes: SS111: Determine whether at least one equipment cooling water subsystem is in operation based on the status parameters of the equipment cooling water system. If so, execute SS112; otherwise, determine the current operating condition as a fault condition. SS112. Determine whether at least one emergency boration subsystem is running based on the status parameters of the emergency boration system. If so, determine that the current operating condition is a fault condition; otherwise, execute SS113. SS113. Determine whether the unit is boronizing at maximum flow rate based on the status parameters of the reactor boron and water supply system. If so, determine that the current operating condition is a fault condition; otherwise, execute SS114. SS114. Determine whether at least one main pump is operating based on the status parameters of the reactor coolant system main pump. If so, determine that the current operating condition is normal operating condition; otherwise, determine that the current operating condition is natural circulation operating condition.

[0022] Preferably, the equipment and system status parameters further include the status parameters of the secondary passive waste heat removal system; In S20, generating a switching signal based on the diagnostic result includes: If the diagnostic result indicates that the primary loop status, primary loop water level, or containment status needs to be downgraded, or if the current operating condition is determined to be a normal operating condition, a switching signal that can represent the switch to the normal operating condition diagram is generated. If the diagnosis result indicates that the nuclear power or secondary loop status needs to be downgraded, a switching signal that can indicate switching to the accident condition diagram is generated. If the diagnosis result indicates that the waste heat removal function needs to be downgraded, a switching signal is generated based on the injection trigger signal and the status parameters of the secondary passive waste heat removal system. If the diagnosis result indicates that the status function needs to be downgraded, a switching signal is generated based on the safety injection system status parameters and the safety injection trigger signal; If the current operating condition is determined to be a fault condition, a switching signal that indicates switching to the fault condition diagram is generated. If the current operating condition is determined to be a natural cycle operating condition, a switching signal is generated that indicates a switch to the natural cycle operating condition diagram.

[0023] Preferably, the injection trigger signal and the secondary-side passive waste heat removal system status parameter generation and switching signal include: SS201: Determine whether all waste heat removal subsystems are running based on the status parameters of the secondary passive waste heat removal system. If yes, execute SS202; otherwise, generate a switching signal that indicates switching to the natural circulation operating condition diagram. SS202. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

[0024] Preferably, generating the switching signal based on the safety injection system status parameters and the safety injection trigger signal includes: SS211. Determine whether at least one safety injection subsystem is running based on the safety injection system status parameters. If so, generate a switching signal that indicates switching to the normal operating condition diagram; otherwise, execute SS212. SS212. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

[0025] The present invention also constructs a control device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to implement the steps of the primary loop pressure-temperature diagram switching method described above.

[0026] The present invention also constructs a computer storage medium storing a computer program, wherein the computer program, when running, implements the steps of the primary loop pressure-temperature diagram switching method described above.

[0027] The technical solution of this invention can automatically switch the primary loop pressure-temperature diagram based on the current state of the unit, effectively reducing the frequent manual switching operations of the operator during the use of the primary loop pressure-temperature diagram, significantly reducing the operator's burden, and also avoiding the situation where the operator mistakenly uses a primary loop pressure-temperature diagram that is not compatible with the current operating conditions when executing the operating procedures to control the unit. This reduces human error caused by the operator in the process of controlling the unit and helps to improve the intelligence level of the nuclear power plant and the safety of unit operation. Attached Figure Description

[0028] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings: Figure 1 This is a flowchart of a method for switching a primary loop pressure-temperature diagram in some embodiments of the present invention; Figure 2 This is a flowchart of a procedure for diagnosing the status of a generator unit based on key parameters in some embodiments of the present invention; Figure 3 This is a flowchart of the primary loop water volume diagnosis procedure in some embodiments of the present invention; Figure 4 This is a flowchart of the primary loop subcooling diagnosis procedure in some embodiments of the present invention; Figure 5 This is a flowchart of the nuclear power diagnosis procedure in some embodiments of the present invention; Figure 6 This is a flowchart of the waste heat extraction function diagnosis in some embodiments of the present invention; Figure 7 This is a flowchart of the state function diagnosis procedure in some embodiments of the present invention; Figure 8 This is a flowchart of the working condition diagnosis procedure in some embodiments of the present invention; Figure 9This is a flowchart of the program for generating switching signals in some embodiments of the present invention; Figure 10 This is a flowchart of the program for generating switching signals in some other embodiments of the present invention. Detailed Implementation

[0029] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0030] It should be noted that the flowcharts shown in the accompanying drawings are merely illustrative and do not necessarily include all content and operations / steps, nor do they necessarily have to be performed in the described order. For example, some operations / steps can be broken down, while others can be combined or partially combined; therefore, the actual execution order may change depending on the specific circumstances.

[0031] The block diagrams shown in the accompanying drawings are merely functional entities and do not necessarily correspond to physically independent entities. That is, these functional entities can be implemented in software, in one or more hardware modules or integrated circuits, or in different network and / or processor devices and / or microcontroller devices.

[0032] This invention provides a method for switching the primary loop pressure-temperature diagram. This method can automatically switch the primary loop pressure-temperature diagram based on the current state of the unit, effectively avoiding frequent manual switching operations by the operator while using the primary loop pressure-temperature diagram. Figure 1 As shown, the switching method includes steps S10, S20 and S30.

[0033] Step S10 includes: acquiring key parameters. These key parameters include status function parameters representing the physical state of the unit, equipment and system status parameters representing the operating state of the primary loop equipment and systems, protection signals representing the reactor status, and alarm signals representing alarm information generated by the equipment and systems. In this step, acquiring key parameters representing the unit's operating status provides data support for determining the unit's current state.

[0034] Furthermore, the status function parameters may include primary coolant saturation margin (ΔTsat), pressure vessel water level (LRPV), steam generator pressure (PSG), steam generator level (LSG), containment pressure, reactor coolant system loop level, primary loop leakage rate, containment dose rate, core outlet temperature, intermediate range power (ICP), emergency shutdown time (RT time), and primary loop pressure (PRCP).

[0035] Equipment and system status parameters may include primary loop status parameters, emergency borosilicate system status parameters, steam generator status parameters, reactor boron and water supply system status parameters, reactor coolant system main pump status parameters, equipment cooling water system status parameters, safety injection system status parameters, and secondary passive residual heat removal system status parameters. It should be noted that each status parameter represents information about the current operating status of the corresponding equipment or system, including whether the equipment or system is in operation (in operation) and what operating mode it is in. For example, whether the primary loop is in a closed state, whether the safety injection system is in residual heat removal mode, whether the safety injection system is in safety injection mode, and whether the reactor coolant system main pump is in operation.

[0036] The protection signals may include a cold overpressure protection signal indicating that cold overpressure protection is allowed to be activated, a waste heat removal allow connection signal indicating that waste heat removal mode is allowed to be connected, a safety injection trigger signal indicating that safety injection mode is allowed to be triggered, and a safety injection switch signal indicating that the mode is switched to safety injection mode.

[0037] Alarm information may include emergency power distribution system alarm information indicating whether the emergency power distribution system is in an emergency alarm state, main steam system high temperature alarm information indicating whether each valve in the main steam system has a high temperature alarm, and radiation monitoring system feedback information indicating whether the radiation dose of various equipment (such as steam generators, coolants, etc.) exceeds the standard.

[0038] Step S20 includes: diagnosing the unit's status based on key parameters and generating a switching signal based on the diagnosis results. This step analyzes the unit's operating status based on key parameters to diagnose the unit's current state, and then generates a switching signal that can control the switching of the primary loop pressure-temperature diagram based on the diagnosed current state.

[0039] In some embodiments, the diagnosis of the unit's status based on key parameters in step S20 may include: diagnosing multiple preset degradation requirements sequentially based on a set diagnostic rule and key parameters, and generating a diagnostic result based on a certain degradation requirement when it is determined that a degradation requirement needs to be downgraded. In this embodiment, the set diagnostic rule can be based on the protection function failure rate gradually decreasing to follow the principle of gradual progress. This allows for a more reasonable switching of the primary loop pressure-temperature diagram, which not only facilitates accurate analysis of the unit's current status by staff but also helps avoid over-protection and unnecessary impacts. For example, the primary loop status, as the first line of defense for nuclear power plant protection, should be prioritized in determining whether the primary loop should be downgraded. Furthermore, it should be noted that "degradation" of a device (or system) indicates a decrease in the protection performance of the corresponding device (or system).

[0040] Furthermore, in some embodiments, such as Figure 2As shown, the specific steps for diagnosing the status of the unit based on key parameters may include steps S201, S202, S203, S204, S205, S206, S207, S208, S209, S2010 and S2011.

[0041] Step S201 includes: performing a first-loop state diagnosis to determine whether the first-loop state needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S202.

[0042] Furthermore, in some embodiments, the primary circuit status diagnosis may include: determining whether the primary circuit is in a closed state based on primary circuit status parameters and determining whether the emergency power distribution system is in an emergency alarm state based on emergency power distribution system alarm information. If the primary circuit is not in a closed state or the emergency power distribution system is in an emergency alarm state, then it is determined that the primary circuit needs to be downgraded; otherwise, it is determined that the primary circuit does not need to be downgraded. In this embodiment, when the primary circuit is not in a closed state or the emergency power distribution system is in an emergency alarm state, it indicates that the protection function of the primary circuit has degraded and should be downgraded; when the primary circuit is in a closed state and the emergency power distribution system is not in an emergency alarm state, it indicates that the protection function of the primary circuit is normal and further diagnosis should be performed, therefore, it is determined that the primary circuit does not need to be downgraded.

[0043] Step S202 includes: performing a primary loop water level diagnosis to determine whether the primary loop water level needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to step S203.

[0044] Furthermore, such as Figure 3 As shown, the specific steps for primary loop water capacity diagnosis may include steps S2021 and S2022.

[0045] Step S2021 includes: determining whether at least one main pump is operating based on the status parameters of the reactor coolant system main pumps; if so, determining that the primary coolant circuit water level does not need to be downgraded; otherwise, proceeding to S2022. In this step, the reactor coolant system includes multiple main pumps. When at least one main pump is operating, it indicates that the primary coolant circuit water level can be basically stably controlled, and therefore the primary coolant circuit water level does not need to be downgraded.

[0046] Step S2022 includes: determining whether the primary coolant saturation margin is less than the fourth set margin value and whether the pressure vessel water level is less than the set water level value. If either criterion is met, the primary coolant charge needs to be downgraded; if neither criterion is met, the primary coolant charge does not need to be downgraded. In this step, when the primary coolant saturation margin is less than the fourth set margin value, it means that superheated steam has appeared in the pressure vessel (the reactor core may be partially exposed), posing a safety hazard, therefore the primary coolant charge must be downgraded; and when the pressure vessel water level is less than the set water level value, it means that the reactor core is about to be exposed or has already begun to be exposed, therefore the primary coolant charge must also be downgraded. The fourth set margin value and the set water level value can be customized by the personnel according to the actual situation of the unit, and are not restricted here.

[0047] Step S203 includes: determining whether the primary coolant saturation margin is greater than a first set margin value; if so, proceeding to S204; otherwise, proceeding to S207. The first set margin value can be the opposite of a fourth set margin value.

[0048] Step S204 includes: performing a primary loop subcooling diagnosis to determine whether the primary loop subcooling needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S205.

[0049] Furthermore, such as Figure 4 As shown, the specific process for primary loop subcooling diagnosis may include the following steps: S2041. Determine whether the cold overpressure protection signal is effective. If yes, execute S2044; otherwise, execute S2042. S2042. Determine whether the waste heat output enable connection signal is effective. If yes, execute S2043; otherwise, execute S2045. S2043. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the safety injection system status parameters. If so, execute S2044; otherwise, determine that the primary loop subcooling does not need to be downgraded (not shown). S2044. Determine whether the primary circuit pressure is greater than the first set pressure value. If so, determine that the primary circuit subcooling needs to be downgraded; otherwise, determine that the primary circuit subcooling does not need to be downgraded. S2045. Determine whether at least one main pump is running based on the status parameters of the reactor coolant system main pump. If yes, proceed to S2046; otherwise, proceed to S2047. S2046. Determine whether the primary coolant saturation margin is greater than the second set margin value. If so, determine that the primary subcooling needs to be downgraded; otherwise, determine that the primary subcooling does not need to be downgraded. S2047. Determine whether the primary coolant saturation margin is greater than the third set margin value. If so, determine that the primary subcooling needs to be downgraded; otherwise, determine that the primary subcooling does not need to be downgraded. Wherein, the third set margin value is less than the second set margin value.

[0050] In this embodiment, when the cold overpressure protection signal and the residual heat removal permission signal are not active, if at least one main pump in the reactor coolant system is operating and the primary coolant saturation margin is greater than the second set margin value, or if none of the main pumps in the reactor coolant system are operating and the primary coolant saturation margin is greater than the third set margin value, it means that the pressure vessel faces the risk of brittle fracture, and therefore the primary coolant subcooling needs to be downgraded. Conversely, when the cold overpressure protection signal is active and the primary pressure is greater than the first set pressure value, or when the cold overpressure protection signal is not active but the residual heat removal permission signal is active and at least one safety injection subsystem in the safety injection system is connected to the residual heat removal pipeline, and the primary pressure is greater than the first set pressure value, it means that an unknown and uncontrollable pressure rise has occurred in the unit, and therefore the primary coolant subcooling also needs to be downgraded. It should be noted that, to comply with the redundancy design principle, existing safety injection systems generally include multiple safety injection subsystems.

[0051] Optionally, the second set margin value is equal to 180°C; the third set margin value is equal to 140°C; and the first set pressure value is equal to 5 MPa.G.

[0052] Step S205 includes: performing a nuclear power diagnosis to determine whether the nuclear power needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S206.

[0053] Furthermore, such as Figure 5 As shown, the specific process of nuclear power diagnostics may include the following steps: S2051. Determine whether the intermediate range power is less than the first set flux. If so, determine that the core power does not need to be downgraded. Otherwise, execute S2052. S2052. Determine if the emergency shutdown time is less than the first set time. If so, execute S2053. Otherwise, determine that the nuclear power needs to be downgraded. S2053. Determine whether the intermediate range power is less than the second set flux. If so, determine that the core power does not need to be downgraded; otherwise, determine that the core power needs to be downgraded.

[0054] In this embodiment, when the intermediate range power is not less than the first set flux and the emergency shutdown time is not less than the first set time, or when the emergency shutdown time is not less than the first set time and the intermediate range power is not less than the second set flux, it means that there are signs of excessive or uncontrolled nuclear power. Therefore, the nuclear power needs to be downgraded in order to prevent the primary coolant from becoming saturated after the nuclear power is downgraded, thereby ensuring the safe operation of the unit.

[0055] Optionally, the first set flux is equal to The first set time is 20 minutes; the second set flux is 3%PN.

[0056] Step S206 includes: performing a waste heat extraction function diagnosis to determine whether waste heat extraction needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S208.

[0057] Furthermore, such as Figure 6 As shown, the specific process for diagnosing the waste heat extraction function may include the following steps: S2061. Determine whether there is at least one safety injection subsystem working in residual heat export mode based on the safety injection system status parameters. If so, determine that residual heat export does not need to be downgraded; otherwise, execute S2062. S2062. Determine whether the waste heat output permission connection signal is effective. If yes, execute S2063; otherwise, execute S2069. S2063. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the safety injection system status parameters. If yes, proceed to S2064; otherwise, proceed to S2069. S2064. Determine whether there is at least one unisolated steam generator with a pressure lower than the second set pressure value based on the steam generator status parameters and steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded. S2065. Determine whether there is at least one unisolated steam generator with a liquid level greater than the first set liquid level based on the steam generator status parameters and the steam generator liquid level. If so, execute S2066; otherwise, determine that the waste heat removal function needs to be downgraded. S2066. Determine if the core outlet temperature is lower than the fourth set temperature. If yes, execute S2067. Otherwise, determine that the residual heat removal function needs to be downgraded. S2067. Determine whether the core outlet temperature is lower than the fifth set temperature. If so, determine that the residual heat removal function does not need to be downgraded; otherwise, execute S2068. S2068. Determine whether a main pump is running based on the status parameters of the reactor coolant system main pump. If so, determine that the residual heat removal function needs to be downgraded; otherwise, determine that the residual heat removal function does not need to be downgraded. S2069. Determine whether there is at least one unisolated steam generator with a pressure lower than the third set pressure value based on the steam generator status parameters and steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded.

[0058] In this embodiment, when no safety injection subsystem is operating in waste heat extraction mode and the waste heat extraction permission connection signal is not active, the unit can be cooled by heat conduction through the steam generator. Therefore, it is necessary to determine the operating status of the steam generator. If the waste heat extraction permission connection signal is active, at least one safety injection subsystem is connected to the waste heat extraction pipeline, and the pressure of any unisolated steam generator is less than the second set pressure value, it indicates that heat conduction cooling through the steam generator has failed, and the waste heat extraction function needs to be degraded. If the waste heat extraction permission connection signal is not active, and the steam generator heat conduction cooling has failed, it may be because there is at least one unisolated steam generator. If the pressure is too high (not less than the third set pressure value) or the steam generator has completely lost its feedwater function (the liquid level of no unisolated steam generator is higher than the first set liquid level), the residual heat removal function also needs to be downgraded. If the liquid level of at least one unisolated steam generator is higher than the first set liquid level, but the core outlet temperature is not lower than the fourth set temperature, the residual heat removal function also needs to be downgraded. If the liquid level of at least one unisolated steam generator is higher than the first set liquid level, but the core outlet temperature is not lower than the fifth set temperature and one main pump is running, it indicates that the steam generator heat conduction cooling may have failed, so the residual heat removal function also needs to be downgraded.

[0059] Optionally, the second set pressure value is equal to 1.4 MPa.G; the third set pressure value is equal to 8.95 MPa.G; the first set liquid level is equal to 2.59 meters; the fourth set temperature is equal to 335℃; and the fifth set temperature is equal to 320℃.

[0060] Step S207 includes: performing a residual heat removal function diagnosis; if it is determined that residual heat removal needs to be downgraded, the diagnosis ends; if it is determined that residual heat removal does not need to be downgraded, then performing a nuclear power diagnosis; if nuclear power needs to be downgraded, the diagnosis ends; if nuclear power does not need to be downgraded, then proceed to S208. The specific processes for the residual heat removal function diagnosis and nuclear power diagnosis performed in this step can be referred to the above text and will not be repeated here.

[0061] Step S208 includes: performing containment status diagnosis to determine whether the containment status needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S209.

[0062] Furthermore, the specific process of containment status diagnosis may include: determining whether the dose rate inside the containment is less than a set dose rate; if so, determining that the containment status does not need to be downgraded; otherwise, determining that the containment status needs to be downgraded. In this embodiment, if the dose rate inside the containment is not less than the set dose rate, it indicates that a large-scale LOCA (Local Occurrence-Altered Collision) accident may have occurred in the primary loop, therefore the containment status needs to be downgraded.

[0063] Optionally, the dose rate is set to 0.02 Gy / h.

[0064] Step S209 includes: performing a second-loop status diagnosis to determine whether the second loop needs to be degraded; if so, the diagnosis ends; otherwise, proceed to S2010.

[0065] Furthermore, the specific process of secondary loop status diagnosis may include: determining, based on feedback information from the radiation monitoring system, whether at least one steam generator has triggered a radioactive alarm; if so, determining that the secondary loop status needs to be downgraded; otherwise, determining that the secondary loop status does not need to be downgraded. In this embodiment, when at least one steam generator triggers a radioactive alarm, it indicates that an anomaly such as a gamma radioactivity alarm may have occurred. In this case, the unit needs to be activated and withdrawn, therefore the secondary loop status needs to be downgraded.

[0066] Step S2010 includes: performing a status function diagnosis to determine whether the status function needs to be downgraded; if so, the diagnosis ends; otherwise, proceed to S2011.

[0067] Furthermore, such as Figure 7 As shown, the specific process of functional status diagnosis may include the following steps: SS101: Determine whether at least one steam generator is unavailable based on the steam generator status parameters. If so, determine that the status function needs to be downgraded; otherwise, execute SS102. SS102. Determine whether the pressure difference between the unisolated steam generators is less than the fourth set pressure value based on the steam generator status and steam generator pressure. If so, execute SS103; otherwise, determine that the status function needs to be downgraded. SS103. Determine whether at least one valve in the main steam system has a high temperature alarm based on the high temperature alarm information of the main steam system. If so, determine that the status function needs to be downgraded; otherwise, execute SS104. SS104. Determine whether the primary coolant saturation margin is greater than the first set margin value. If so, execute SS105; otherwise, determine that the status function needs to be downgraded. SS105. Determine if the injection switching signal is effective. If yes, execute SS106; otherwise, execute SS1010. SS106. Determine if the injection trigger signal is effective. If so, execute SS107; otherwise, determine if the status function needs to be downgraded. SS107: Determine if the reactor coolant system loop level is greater than the second set level. If so, execute SS108; otherwise, determine if the status function needs to be downgraded. SS108. Determine if the primary loop leakage rate is greater than the set leakage rate. If so, determine that the status function needs to be downgraded; otherwise, execute SS109. SS109. Determine whether the containment pressure is less than the fifth set pressure value. If so, the determination function does not need to be downgraded; otherwise, the determination function needs to be downgraded. SS1010: Determine if the voltage regulator pressure is greater than the sixth set pressure value. If so, determine if the status function needs to be downgraded; otherwise, execute SS108.

[0068] In this embodiment, if at least one steam generator is unavailable or the pressure difference between unisolated steam generators is less than the fourth set pressure value, it is presumed that there may be an accident such as a main feedwater pipeline rupture or a main steam pipeline rupture, which would cause the pressure of the affected steam generator to drop, and the status function needs to be downgraded. If at least one main steam system valve triggers a high-temperature alarm, it is presumed that there may be an accident such as a main steam pipeline rupture outside the containment, and the status function also needs to be downgraded. If no rupture accident occurs, the activation conditions for safety injection are further checked. If the safety injection switching signal is active but the safety injection trigger signal is not active, the status function needs to be downgraded. If the safety injection trigger signal is active and the reactor coolant system loop level is greater than the second set level, the status function also needs to be downgraded. If the containment pressure is not less than the fifth set pressure value (indicating the presence of mass energy release within the containment), it indicates that there may be an accident such as a primary loop pipeline rupture, a steam pipeline rupture within the containment, or a SG feedwater pipeline rupture, and the status function also needs to be downgraded.

[0069] Optionally, the fourth set pressure value is equal to 1 MPa; the second set liquid level is equal to 0.45 meters; the fifth set pressure value is equal to 0.12 MPa.a; and the sixth set pressure value is equal to 11.4 MPa.G.

[0070] Step S2011 includes: performing a working condition diagnosis to determine the current working condition, and the diagnosis ends; wherein, the current working condition includes a fault working condition, a normal operating condition, and a natural cycle working condition.

[0071] Furthermore, such as Figure 8 As shown, the specific process of operating condition diagnosis may include the following steps: SS111: Determine whether at least one equipment cooling water subsystem is in operation based on the equipment cooling water system status parameters. If so, execute SS112; otherwise, determine the current operating condition as a fault condition. SS112. Determine whether at least one emergency boration subsystem is running based on the status parameters of the emergency boration system. If so, determine that the current operating condition is a fault condition; otherwise, execute SS113. SS113. Determine whether the unit is boronizing at maximum flow rate based on the status parameters of the reactor boron and water supply system. If so, determine the current operating condition as a fault condition; otherwise, execute SS114. SS114. Determine whether at least one main pump is operating based on the status parameters of the reactor coolant system main pumps. If so, determine that the current operating condition is normal operating condition; otherwise, determine that the current operating condition is natural circulation operating condition.

[0072] In this embodiment, if all equipment cooling water subsystems in the equipment cooling water system are shut down (not in operation), the unit will not be able to retreat to the residual heat removal cooling intermediate shutdown condition because the heat exchanger in the safety injection system has lost its cooling function. At this time, the current operating condition is determined to be a fault condition. If the unit is boronizing, that is, if at least one emergency boronizing subsystem is running in the emergency boronizing system or the reactor boron and water supply system is boronizing at maximum flow, it indicates that there is a need to retreat. At this time, the current operating condition is also determined to be a fault condition to avoid triggering the safety injection system during the retreat. If no emergency boronizing subsystem is running and the reactor boron and water supply system is not running, the current operating condition is determined according to the operating status of the reactor coolant system main pump. If at least one main pump is running, the current operating condition is determined to be a normal operating condition; otherwise, the current operating condition is determined to be a natural circulation condition.

[0073] In some embodiments, the specific steps for generating a switching signal based on the diagnostic results include steps SS221, SS222, SS223, SS224, SS225, and SS226.

[0074] Step SS221 includes: if the diagnostic result indicates that the primary loop status, primary loop water level, or containment status needs to be degraded, or if the current operating condition is determined to be normal operating condition, then a switching signal capable of indicating a switch to the normal operating condition diagram is generated. In this step, when the primary loop water level and containment status need to be degraded, since the safety injection system has already been triggered, the use of the primary loop pressure-temperature diagram is not considered; therefore, a switching signal capable of controlling the switch to the normal operating condition diagram needs to be generated.

[0075] Step SS222 includes: if the diagnostic result indicates that the nuclear power or secondary loop status needs to be downgraded, then a switching signal that indicates a switch to the accident condition diagram is generated. In this step, when the nuclear power needs to be downgraded, a switching signal that controls the switch to the accident condition diagram needs to be generated to prevent the primary loop coolant from saturating; and when the secondary loop status needs to be downgraded, a switching signal that controls the switch to the accident condition diagram also needs to be generated because the unit needs to be withdrawn.

[0076] Step SS223 includes: if the diagnostic result indicates that the waste heat removal function needs to be downgraded, a switching signal is generated based on the injection trigger signal and the status parameters of the secondary passive waste heat removal system.

[0077] Furthermore, in some embodiments, such as Figure 9 As shown, the specific process of generating a switching signal based on the safety injection trigger signal and the status parameters of the secondary passive waste heat removal system may include the following steps: SS201: Determine whether all waste heat removal subsystems are running based on the status parameters of the secondary passive waste heat removal system. If so, execute SS202; otherwise, generate a switching signal that indicates switching to the natural circulation operating condition diagram. SS202. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

[0078] As is easy to understand, the "Safety Injection Trigger Signal Not Effective Fault Condition Diagram" means that in addition to displaying the fault condition diagram, it also shows that the safety injection trigger signal has taken effect. Conversely, the "Safety Injection Trigger Signal Not Effective Fault Condition Diagram" means that in addition to displaying the fault condition diagram, it also shows that the safety injection trigger signal has not taken effect. This allows staff to monitor the current operating condition by combining the status of the safety injection trigger signal.

[0079] Step SS224 includes: if the diagnostic result indicates that the status function needs to be downgraded, then a switching signal is generated based on the safety injection system status parameters and the safety injection trigger signal.

[0080] Furthermore, in some embodiments, such as Figure 10 As shown, the specific process of generating a switching signal based on the safety injection system status parameters and the safety injection trigger signal may include the following steps: SS211. Determine whether at least one safety injection subsystem is running based on the safety injection system status parameters. If so, generate a switching signal that indicates switching to the normal operating condition diagram; otherwise, execute SS212. SS212. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

[0081] Step SS225 includes: if the current operating condition is determined to be a fault operating condition, then generating a switching signal that can indicate switching to the fault operating condition diagram; Step SS226 includes: if the current operating condition is determined to be a natural cycle operating condition, then generating a switching signal that can indicate the switch to the natural cycle operating condition diagram.

[0082] Step S30 includes: switching the primary loop pressure-temperature diagram according to the switching signal, and returning to S10. After switching the primary loop pressure-temperature diagram, this step will return to step S10 to cycle through steps S10 to S30, thereby continuously and automatically controlling the switching of the primary loop pressure-temperature diagram.

[0083] The present invention also provides a control device, including a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, it implements the steps of the primary loop pressure-temperature map switching method of the present invention.

[0084] The present invention also provides a computer storage medium storing a computer program, wherein the computer program, when running, implements the steps of the primary loop pressure-temperature diagram switching method of the present invention.

[0085] The technical solution of this invention can automatically switch the primary loop pressure-temperature diagram based on the current state of the unit, effectively reducing the frequent manual switching operations of the operator during the use of the primary loop pressure-temperature diagram, significantly reducing the operator's burden, and also avoiding the situation where the operator mistakenly uses a primary loop pressure-temperature diagram that is not compatible with the current operating conditions when executing the operating procedures to control the unit. This reduces human error caused by the operator in the process of controlling the unit and helps to improve the intelligence level of the nuclear power plant and the safety of unit operation.

[0086] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0087] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0088] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0089] It is understood that the above embodiments only illustrate preferred embodiments of the present invention, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present invention. It should be noted that those skilled in the art can freely combine the above technical features without departing from the concept of the present invention, and can also make several modifications and improvements, all of which fall within the protection scope of the present invention. Therefore, all equivalent transformations and modifications made with respect to the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A method for switching primary loop pressure-temperature diagrams, characterized in that, Includes the following steps: S10. Obtain key parameters; wherein, the key parameters include status function parameters that can represent the physical state of the unit, equipment and system status parameters that can represent the operating state of the primary loop equipment and system, protection signals that can represent the reactor state, and alarm signals that can represent the alarm information generated by the equipment and system. S20. Diagnose the status of the unit based on the key parameters and generate a switching signal based on the diagnosis results; S30. Switch the primary loop pressure-temperature diagram according to the switching signal and return to S10; In step S20, the step of diagnosing the status of the unit based on the key parameters includes: Based on the established diagnostic rules and the key parameters, a variety of preset degradation requirements are diagnosed sequentially, and when it is determined that a certain degradation requirement needs to be downgraded, a diagnostic result is generated based on that certain degradation requirement. In step S20, diagnosing the unit's status based on the key parameters includes: S201. Perform a primary loop state diagnosis to determine whether the primary loop state needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S202. S202. Perform a primary loop water capacity diagnosis to determine whether the primary loop water capacity needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S203. S203. Determine whether the saturation margin of the primary coolant circuit is greater than the first set margin value. If yes, execute S204; otherwise, execute S207. S204. Perform a primary loop subcooling diagnosis to determine whether the primary loop subcooling needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S205. S205. Perform nuclear power diagnosis to determine whether nuclear power needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S206. S206. Perform waste heat extraction function diagnosis to determine whether waste heat extraction needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S208. S207. Perform waste heat export function diagnosis. If it is determined that the waste heat export needs to be downgraded, the diagnosis ends. If it is determined that the waste heat export does not need to be downgraded, perform the nuclear power diagnosis. If the nuclear power needs to be downgraded, the diagnosis ends. If the nuclear power does not need to be downgraded, proceed to S208. S208. Perform containment status diagnosis to determine whether the containment status needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S209. S209. Perform a second-loop status diagnosis to determine whether the second loop needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S2010. S2010. Perform status function diagnosis to determine whether the status function needs to be downgraded. If so, the diagnosis ends; otherwise, proceed to S2011. S2011. Perform operating condition diagnosis to determine the current operating condition, and the diagnosis ends; wherein, the current operating condition includes fault operating condition, normal operating condition and natural cycle operating condition.

2. The method for switching the primary loop pressure-temperature diagram according to claim 1, characterized in that, In S10, the status function parameters include primary coolant saturation margin, pressure vessel water level, steam generator pressure, steam generator liquid level, containment pressure, reactor coolant system loop liquid level, primary loop leakage rate, containment dose rate, core outlet temperature, intermediate range power, emergency shutdown time, and primary loop pressure. The equipment and system status parameters include primary loop status parameters, emergency boronizing system status parameters, steam generator status parameters, reactor boron and water supply system status parameters, reactor coolant system main pump status parameters, equipment cooling water system status parameters, and safety injection system status parameters. The protection signals include a cold overpressure protection signal, a waste heat discharge permission signal, a safety injection trigger signal, and a safety injection switching signal. The alarm information includes alarm information from the emergency power distribution system, high temperature alarm information from the main steam system, and feedback information from the radiation monitoring system.

3. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S201, the first-loop status diagnosis includes: determining whether the first-loop is in a closed state based on the first-loop status parameters and determining whether the emergency power distribution system is in an emergency alarm state based on the emergency power distribution system alarm information. If the first-loop is not in a closed state or the emergency power distribution system is in an emergency alarm state, then the first-loop is determined to require degradation; otherwise, the first-loop is determined not to require degradation.

4. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S202, the primary loop water level diagnosis includes: S2021. Determine whether at least one main pump is running based on the status parameters of the reactor coolant system main pump. If so, determine that the primary loop water loading does not need to be downgraded; otherwise, proceed to S2022. S2022. Determine whether the saturation margin of the primary coolant is less than the fourth set margin value and whether the water level of the pressure vessel is less than the set water level value. If either criterion is met, it is determined that the water volume of the primary coolant needs to be downgraded. If neither criterion is met, it is determined that the water volume of the primary coolant does not need to be downgraded.

5. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S204, the primary loop subcooling diagnosis includes: S2041. Determine whether the cold overpressure protection signal is effective. If yes, execute S2044; otherwise, execute S2042. S2042. Determine whether the waste heat output permission connection signal is effective. If yes, execute S2043; otherwise, execute S2045. S2043. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the status parameters of the safety injection system. If so, execute S2044. S2044. Determine whether the pressure of the primary circuit is greater than the first set pressure value. If so, determine that the subcooling of the primary circuit needs to be downgraded; otherwise, determine that the subcooling of the primary circuit does not need to be downgraded. S2045. Determine whether at least one main pump is running based on the status parameters of the reactor coolant system main pump. If yes, proceed to S2046; otherwise, proceed to S2047. S2046. Determine whether the saturation margin of the primary coolant circuit is greater than the second set margin value. If so, determine that the primary circuit subcooling needs to be downgraded; otherwise, determine that the primary circuit subcooling does not need to be downgraded. S2047. Determine whether the saturation margin of the primary coolant circuit is greater than the third set margin value. If so, determine that the primary circuit subcooling needs to be downgraded; otherwise, determine that the primary circuit subcooling does not need to be downgraded. Wherein, the third set margin value is less than the second set margin value.

6. The method for switching the primary loop pressure-temperature diagram according to claim 5, characterized in that, In S204, the second set margin value is equal to 180°C; and / or the third set margin value is equal to 140°C; and / or the first set pressure value is equal to 5 MPa.G.

7. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S205, the nuclear power diagnosis includes: S2051. Determine whether the intermediate range power is less than the first set flux. If so, determine that the nuclear power does not need to be downgraded. Otherwise, execute S2052. S2052. Determine whether the emergency shutdown time is less than the first set time. If so, execute S2053; otherwise, determine that the nuclear power needs to be downgraded. S2053. Determine whether the intermediate range power is less than the second set flux. If so, determine that the core power does not need to be downgraded; otherwise, determine that the core power needs to be downgraded.

8. The method for switching the primary loop pressure-temperature diagram according to claim 7, characterized in that, In S205, the first set flux is equal to ; and / or the first set time is equal to 20 minutes; and / or the second set flux is equal to 3%PN.

9. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In the 206th step, the waste heat removal function diagnosis includes: S2061. Determine whether there is at least one safety injection subsystem working in waste heat export mode based on the safety injection system status parameters. If so, determine that waste heat export does not need to be downgraded; otherwise, execute S2062. S2062. Determine whether the waste heat output permission connection signal is effective. If yes, execute S2063; otherwise, execute S2069. S2063. Determine whether at least one safety injection subsystem is connected to the waste heat discharge pipeline based on the status parameters of the safety injection system. If yes, execute S2064; otherwise, execute S2069. S2064. Determine whether there is at least one unisolated steam generator with a pressure lower than the second set pressure value based on the steam generator status parameters and the steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded. S2065. Based on the steam generator status parameters and the steam generator liquid level, determine whether there is at least one unisolated steam generator with a liquid level greater than the first set liquid level. If so, execute S2066; otherwise, determine that the waste heat removal function needs to be downgraded. S2066. Determine whether the core outlet temperature is lower than the fourth set temperature. If yes, execute S2067. Otherwise, determine that the residual heat removal function needs to be downgraded. S2067. Determine whether the core outlet temperature is lower than the fifth set temperature. If so, determine that the residual heat removal function does not need to be downgraded; otherwise, execute S2068. S2068. Determine whether a main pump is running based on the status parameters of the reactor coolant system main pump. If so, determine that the waste heat removal function needs to be downgraded; otherwise, determine that the waste heat removal function does not need to be downgraded. S2069. Determine whether there is at least one unisolated steam generator with a pressure lower than the third set pressure value based on the steam generator status parameters and the steam generator pressure. If so, execute S2065; otherwise, determine that the waste heat removal function needs to be downgraded.

10. The method for switching the primary loop pressure-temperature diagram according to claim 9, characterized in that, In the 206 setting, the second set pressure value is equal to 1.4 MPa.G; and / or the third set pressure value is equal to 8.95 MPa.G; and / or the first set liquid level is equal to 2.59 meters; and / or the fourth set temperature is equal to 335°C; and / or the fifth set temperature is equal to 320°C.

11. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In the 208th statement, the containment condition diagnosis includes: Determine whether the dose rate inside the containment is less than the set dose rate. If so, determine that the containment status does not need to be downgraded; otherwise, determine that the containment status needs to be downgraded.

12. The method for switching the primary loop pressure-temperature diagram according to claim 11, characterized in that, In S209, the second-loop status diagnosis includes: Based on the feedback information from the radiation monitoring system, it is determined whether at least one steam generator has triggered a radiation alarm. If so, the secondary loop status needs to be downgraded; otherwise, the secondary loop status does not need to be downgraded.

13. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S2010, the status function diagnosis includes: SS101: Determine whether at least one steam generator is unavailable based on the steam generator status parameters. If so, determine that the status function needs to be downgraded; otherwise, execute SS102. SS102. Determine whether the pressure difference between the unisolated steam generators is less than the fourth set pressure value based on the steam generator status and the steam generator pressure. If so, execute SS103; otherwise, determine that the status function needs to be downgraded. SS103. Determine whether at least one valve in the main steam system has a high temperature alarm based on the high temperature alarm information of the main steam system. If so, determine that the status function needs to be downgraded; otherwise, execute SS104. SS104. Determine whether the saturation margin of the primary coolant circuit is greater than the first set margin value. If so, execute SS105; otherwise, determine that the status function needs to be downgraded. SS105. Determine whether the injection switching signal is effective. If yes, execute SS106; otherwise, execute SS1010. SS106. Determine whether the injection trigger signal is effective. If yes, execute SS107; otherwise, determine that the status function needs to be downgraded. SS107. Determine whether the reactor coolant system loop liquid level is greater than the second set liquid level. If so, execute SS108; otherwise, determine that the status function needs to be downgraded. SS108. Determine whether the leakage rate of the primary loop is greater than the set leakage rate. If so, determine that the status function needs to be downgraded; otherwise, execute SS109. SS109. Determine whether the containment pressure is less than the fifth preset pressure value. If so, the determination state function does not need to be downgraded; otherwise, the determination state function needs to be downgraded. SS1010: Determine if the voltage regulator pressure is greater than the sixth set pressure value. If so, determine if the status function needs to be downgraded; otherwise, execute SS108.

14. The method for switching the primary loop pressure-temperature diagram according to claim 13, characterized in that, In S2010, the fourth set pressure value is equal to 1 MPa; and / or the second set liquid level is equal to 0.45 meters; and / or the fifth set pressure value is equal to 0.12 MPa.a; and / or the sixth set pressure value is equal to 11.4 MPa.G.

15. The method for switching the primary loop pressure-temperature diagram according to claim 2, characterized in that, In S2011, the operating condition diagnosis includes: SS111: Determine whether at least one equipment cooling water subsystem is in operation based on the status parameters of the equipment cooling water system. If so, execute SS112; otherwise, determine the current operating condition as a fault condition. SS112. Determine whether at least one emergency boration subsystem is running based on the status parameters of the emergency boration system. If so, determine that the current operating condition is a fault condition; otherwise, execute SS113. SS113. Determine whether the unit is boronizing at maximum flow rate based on the status parameters of the reactor boron and water supply system. If so, determine that the current operating condition is a fault condition; otherwise, execute SS114. SS114. Determine whether at least one main pump is operating based on the status parameters of the reactor coolant system main pump. If so, determine that the current operating condition is normal operating condition; otherwise, determine that the current operating condition is natural circulation operating condition.

16. The method for switching primary loop pressure-temperature diagrams according to any one of claims 2 to 12, characterized in that, The equipment and system status parameters also include the status parameters of the secondary passive waste heat removal system. In S20, generating a switching signal based on the diagnostic result includes: If the diagnostic result indicates that the primary loop status, primary loop water level, or containment status needs to be downgraded, or if the current operating condition is determined to be a normal operating condition, a switching signal that can represent the switch to the normal operating condition diagram is generated. If the diagnosis result indicates that the nuclear power or secondary loop status needs to be downgraded, a switching signal that can indicate switching to the accident condition diagram is generated. If the diagnosis result indicates that the waste heat removal function needs to be downgraded, a switching signal is generated based on the injection trigger signal and the status parameters of the secondary passive waste heat removal system. If the diagnosis result indicates that the status function needs to be downgraded, a switching signal is generated based on the safety injection system status parameters and the safety injection trigger signal; If the current operating condition is determined to be a fault condition, a switching signal that indicates switching to the fault condition diagram is generated. If the current operating condition is determined to be a natural cycle operating condition, a switching signal is generated that indicates a switch to the natural cycle operating condition diagram.

17. The method for switching the primary loop pressure-temperature diagram according to claim 16, characterized in that, The safety injection trigger signal and the secondary passive waste heat removal system status parameter generation and switching signal include: SS201: Determine whether all waste heat removal subsystems are running based on the status parameters of the secondary passive waste heat removal system. If yes, execute SS202; otherwise, generate a switching signal that indicates switching to the natural circulation operating condition diagram. SS202. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

18. The method for switching the primary loop pressure-temperature diagram according to claim 16, characterized in that, The step of generating a switching signal based on the safety injection system status parameters and the safety injection trigger signal includes: SS211. Determine whether at least one safety injection subsystem is running based on the safety injection system status parameters. If so, generate a switching signal that indicates switching to the normal operating condition diagram; otherwise, execute SS212. SS212. Determine whether the safety injection trigger signal is effective. If so, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is effective. Otherwise, generate a switching signal that indicates a fault condition diagram where the safety injection trigger signal is not effective.

19. A control device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the steps of the primary loop pressure-temperature map switching method as described in any one of claims 1 to 18.

20. A computer storage medium, characterized in that, The device contains a computer program that, when executed, implements the steps of the primary loop pressure-temperature diagram switching method as described in any one of claims 1 to 18.

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