Nuclear power unit primary loop state monitoring method and related equipment
By constructing a target operating boundary for the coolant in the primary loop of a nuclear power unit and using average temperature and pressure to determine the state, the complex state monitoring problem in existing technologies has been solved, achieving simplified and accurate state monitoring.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-09-11
- Publication Date
- 2026-03-13
AI Technical Summary
Existing methods for monitoring the condition of the primary loop in nuclear power units are complex, requiring the detection of multiple equipment parameters and complex analysis.
By acquiring the equipment parameters of the steam generator, pressure regulator, and waste heat removal system, as well as the temperature, pressure, and saturation set of the coolant under natural circulation conditions, the target operating boundary of the coolant is constructed. The operating status can be determined simply by monitoring whether the average temperature and pressure are within the boundary.
The status monitoring process has been simplified, improving the ease of operation and accuracy of monitoring, and enabling rapid determination of whether the primary circuit is operating abnormally.
Smart Images
Figure CN121662446A_ABST
Abstract
Description
Technical Field
[0001] This application belongs to the field of nuclear power technology, specifically relating to a condition monitoring method and related equipment for the primary loop of a nuclear power unit. Background Technology
[0002] The primary function of a nuclear power unit is to circulate the coolant, transfer the heat generated by nuclear fission in the reactor core to the secondary loop, and cool the reactor core to prevent fuel elements from burning or being damaged.
[0003] Under normal operating conditions in the primary loop, the coolant circulates within the loop under the action of a drive device such as an electric pump. When the drive device is not running, although the coolant cannot circulate under the action of the drive device, the coolant can automatically circulate within the primary loop due to the temperature difference between the coolant in the cold pipe section and the coolant in the hot pipe section. This state is called the natural circulation state of the primary loop.
[0004] In related technologies, in order to ensure the accuracy of condition monitoring results, the operating status of the primary loop is generally determined by detecting the operating parameters of all devices in the primary loop. This requires detecting a large number of parameters, and each parameter needs to be analyzed, making the condition monitoring process quite complex. Summary of the Invention
[0005] The purpose of this application is to provide a condition monitoring method and related equipment for the primary loop of a nuclear power unit, which can solve the problem that the monitoring process of existing condition monitoring methods is relatively complex.
[0006] In a first aspect, embodiments of this application provide a method for monitoring the condition of the primary loop of a nuclear power unit, the primary loop including a steam generator, a pressurizer, and a waste heat removal system, the method comprising:
[0007] When the first loop is in a natural circulation state, the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, the third equipment parameters of the waste heat removal system, and the first information are obtained. The first information includes the temperature and pressure saturation set of the coolant in the first loop. The temperature and pressure saturation set includes the temperature value of the coolant in a saturated state at the pressure value corresponding to each saturation point under multiple saturation points.
[0008] The average temperature and average pressure of the coolant are detected, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time.
[0009] Based on the thermal safety margin of the first loop and the first information, the first operating boundary is determined;
[0010] Based on the first device parameters and the first information, the second operating boundary is determined;
[0011] Based on the second device parameters and the first information, the third operating boundary is determined;
[0012] Based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, the target operating boundary of the coolant is determined, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
[0013] Secondly, embodiments of this application provide a condition monitoring device for the primary loop of a nuclear power unit, the primary loop including a steam generator, a pressurizer, and a waste heat removal system, the device comprising:
[0014] The acquisition module is used to acquire the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, and the third equipment parameters of the waste heat removal system when the first loop is in a natural circulation state, and to acquire first information, the first information including the temperature and pressure saturation set of the coolant in the first loop, the temperature and pressure saturation set including the temperature value of the coolant in a saturated state at the pressure value corresponding to each saturation point under multiple saturation points.
[0015] The detection module is used to detect the average temperature and average pressure of the coolant, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time.
[0016] The first determining module is used to determine the first operating boundary based on the thermal safety margin of the first loop and the first information;
[0017] The second determining module is used to determine the second operating boundary based on the first device parameters and the first information;
[0018] The third determining module is used to determine the third operating boundary based on the second device parameters and the first information;
[0019] The fourth determining module is used to determine the target operating boundary of the coolant based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
[0020] Thirdly, embodiments of this application provide an electronic device, which includes a processor, a memory, and a program stored in the memory and executable on the processor. When the program is executed by the processor, it implements the steps of the state monitoring method for the primary loop of a nuclear power unit as described in the first aspect.
[0021] Fourthly, embodiments of this application provide a computer-readable storage medium storing a computer program, which, when executed by a processor, implements the steps of the state monitoring method for the primary loop of a nuclear power unit as described in the first aspect.
[0022] Fifthly, a computer program product is provided, including computer instructions that, when executed by a processor, implement the steps of the state monitoring method for the primary loop of a nuclear power unit as described in the first aspect.
[0023] In this embodiment, the target operating boundary of the coolant is constructed by acquiring the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, the third equipment parameters of the waste heat removal system, and the first information including the temperature and pressure saturation set of the coolant. When performing state monitoring, it is only necessary to monitor the average temperature and average pressure of the coolant in the natural circulation state of the primary loop. By checking whether the average temperature and average pressure are within the target operating boundary, it is determined whether the operation of the loop in the natural circulation state is abnormal. Compared with the prior art, which requires detecting the operating parameters of all equipment in the primary loop and then analyzing whether each operating parameter is abnormal, the method of this embodiment simplifies the monitoring process. Attached Figure Description
[0024] To more clearly illustrate the technical solutions of the embodiments of this application, the drawings used in the description of the embodiments of this application will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.
[0025] Figure 1 A flowchart illustrating the condition monitoring method for the primary loop of a nuclear power unit provided in this application embodiment;
[0026] Figure 2 This is a schematic diagram of the water saturation curve;
[0027] Figure 3 This is a monitoring diagram of the natural cycle state;
[0028] Figure 4 This is a schematic diagram of the undersaturation limit line for a single loop.
[0029] Figure 5This is a schematic diagram of the undersaturation limit line of the modified primary loop;
[0030] Figure 6 This is a schematic diagram of the pressure differential limit line between the primary and secondary sides of the steam generator;
[0031] Figure 7 This is a schematic diagram of the structure of the condition monitoring device for the primary loop of a nuclear power unit provided in an embodiment of this application;
[0032] Figure 8 This is a schematic diagram of the structure of an electronic device provided in an embodiment of this application. Detailed Implementation
[0033] The technical solutions of the embodiments of this application will be clearly described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of this application. All other embodiments obtained by those skilled in the art based on the embodiments of this application are within the scope of protection of this application.
[0034] The terms "first," "second," etc., used in the specification and claims of this application are used to distinguish similar objects and not to describe a specific order or sequence. It should be understood that such use of data can be interchanged where appropriate so that embodiments of this application can be implemented in orders other than those illustrated or described herein, and the objects distinguished by "first," "second," etc., are generally of the same class and the number of objects is not limited; for example, a first object can be one or more. Furthermore, in the specification and claims, "and / or" indicates at least one of the connected objects, and the character " / " generally indicates that the preceding and following objects are in an "or" relationship.
[0035] The following description, in conjunction with the accompanying drawings, details the nuclear power unit primary loop condition monitoring method provided in this application through specific embodiments and application scenarios. The primary loop includes a main pump, a steam generator, a pressurizer, and a waste heat removal system. Under normal operating conditions, the main pump drives the coolant to circulate within the primary loop; under natural circulation conditions, the main pump is not operational, and the coolant circulates due to the temperature difference between the cold and hot pipe sections.
[0036] like Figure 1 The diagram shown is a schematic flowchart of the state monitoring method for the primary loop of a nuclear power unit provided in this application embodiment, which specifically includes the following steps:
[0037] Step 101: When the primary loop is in a natural circulation state, acquire the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, the third equipment parameters of the waste heat removal system, and acquire first information. The first information includes the temperature and pressure saturation set of the coolant in the primary loop. The temperature and pressure saturation set includes the temperature value of the coolant in a saturated state at the pressure value corresponding to each saturation point under multiple saturation points.
[0038] The first equipment parameter, the second equipment parameter, and the third equipment parameter all refer to the rated parameters of the corresponding equipment that are determined after the equipment is manufactured.
[0039] A coolant is a medium used to absorb and remove the heat generated by nuclear reactor fuel. Commonly used coolants include water and helium. In the following embodiments of this application, water is used as an example to illustrate the method of this application.
[0040] like Figure 2 As shown, the temperature and pressure saturation set of water (coolant) can be represented graphically. Based on the pressure and temperature values at each saturation point, the corresponding saturation point can be plotted on a coordinate system. All saturation points can be depicted as a curve, i.e. Figure 2 The water saturation curve is shown.
[0041] Step 102: Detect the average temperature and average pressure of the coolant, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time.
[0042] In this step, the average temperature and average pressure of the coolant in the primary loop under natural circulation are measured. These two data can reflect the state of the coolant and thus the operating state of the primary loop.
[0043] Step 103: Determine the first operating boundary based on the thermal safety margin of the first loop and the first information.
[0044] Step 104: Determine the second operating boundary based on the first device parameters and the first information.
[0045] Step 105: Determine the third operating boundary based on the second device parameters and the first information.
[0046] During primary loop operation, the pressurizer controls the primary loop pressure through spraying and electric heating. The upper part contains saturated steam, and the lower part contains saturated water. The water pressure and temperature are moderate and fall within the water saturation curve. The circulating water on the secondary side of the steam generator is heated by the coolant (water) from the primary side through a U-tube heat transfer process, becoming a steam-water mixture. The pressure and temperature in the steam generator also fall within the water saturation curve. In other words, when considering the safe operation of the pressurizer and steam generator and needing to limit the temperature and pressure of the coolant, the water saturation curve is the fundamental reference. In steps 103-105 above, the limitations on the temperature and pressure of the coolant were considered to meet the conditions of thermal safety margin, safe operation of the steam generator, and safe operation of the pressurizer, respectively, resulting in the first operating boundary, the second operating boundary, and the third operating boundary.
[0047] Step 106: Based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, determine the target operating boundary of the coolant, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
[0048] Based on the first, second, and third operating boundaries, and taking into account the selection of the waste heat removal system and the limitations of material properties on the temperature and pressure of the coolant, the target operating boundary is obtained.
[0049] like Figure 3 The diagram shown is a natural cycle state monitoring diagram. The target operating boundary can be the range enclosed by curves 2, 3, 4, 5, and 8, that is, the range to the right of curves 3 and 5, above curve 2, to the left of curve 8, and below curve 4.
[0050] When the average temperature and average pressure of the coolant are within the target operating limits, it indicates that there is no abnormality in the operation of the primary circuit; when the average temperature and average pressure of the coolant are not within the target operating limits, an alarm message can be issued, indicating that there is an abnormality in the operation of the primary circuit, reminding the staff to conduct further investigation.
[0051] In the nuclear power unit primary loop condition monitoring method of this application embodiment, the target operating boundary of the coolant is constructed by acquiring the first equipment parameters of the steam generator, the second equipment parameters of the pressurizer, the third equipment parameters of the waste heat removal system, and the first information including the temperature, pressure and saturation set of the coolant. When performing condition monitoring, it is only necessary to monitor the average temperature and average pressure of the coolant in the primary loop natural circulation state. By judging whether the average temperature and average pressure are within the target operating boundary, it is determined whether the operation of the loop in the natural circulation state is abnormal. Compared with the prior art, which requires detecting the operating parameters of all equipment in the primary loop and then analyzing whether each operating parameter is abnormal, the method of this application embodiment simplifies the monitoring process.
[0052] Optionally, step 103, based on the thermal safety margin of the primary loop and the first information, determines the first operating boundary, including:
[0053] Based on the thermal safety margin, the temperature values of the multiple saturation points are updated to obtain multiple updated first saturation points. The temperature value obtained by subtracting the thermal safety margin from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated first saturation point.
[0054] The first operating boundary is determined based on the multiple updated first saturation points;
[0055] Wherein, the first operating boundary includes: when the average pressure is the same as the pressure corresponding to the first target saturation point, the average temperature is less than the temperature corresponding to the first target saturation point, and the first target saturation point is any one of the plurality of updated first saturation points.
[0056] During the operation of the primary loop of a nuclear power unit, except for the pressurizer which is a two-phase system (vapor and liquid), all other parts of the primary loop should be in a liquid state. The average temperature T of the coolant... avg Restrictions will be imposed:
[0057] T avg ≤T sat -ΔT,
[0058] Among them, T sat Let ΔT be the saturation temperature at any operating pressure, and ΔT be the thermal safety margin. Meeting these conditions prevents coolant boiling and avoids localized vaporization at the main pump inlet, which could cause pump cavitation and damage to the blades.
[0059] like Figure 4 As shown, based on the thermal safety margin, the water saturation curve is shifted to the left to obtain the primary loop undersaturation limit line. Figure 3In the diagram, the water saturation curve is curve 1, and the primary loop undersaturation limit line is curve 2. The first operating boundary is defined as the average pressure and average temperature of the coolant to the left of the primary loop undersaturation limit line.
[0060] Optionally, the temperature of the second target saturation point is greater than or equal to the hot zero-power temperature of the coolant, and the pressure of the third target saturation point is less than or equal to the hot zero-power pressure of the coolant.
[0061] Wherein, the second target saturation point is the saturation point in the plurality of updated first saturation points whose pressure is the same as the thermal zero-power pressure, and the third target saturation point is the saturation point in the plurality of updated first saturation points whose temperature is the same as the thermal zero-power temperature.
[0062] Understandably, the thermal safety margin determines the first operating boundary. In the primary loop undersaturation limit line obtained after shifting the water saturation curve based on the thermal safety margin, the temperature of the second target saturation point is greater than or equal to the hot zero-power temperature of the coolant, and the pressure of the third target saturation point is less than or equal to the hot zero-power pressure of the coolant. For example... Figure 4 As shown, the hot zero-power temperature is T0, and the hot zero-power pressure is P0. If the thermal safety margin is too large, the water saturation curve shifts too far to the left, and the resulting primary loop undersaturation limit line intersects the hot zero-power pressure line P0 at point N. Theoretically, this should be achieved by increasing the temperature while maintaining the primary loop pressure, allowing the coolant to reach the hot zero-power state, but this is difficult to achieve in practice. If the thermal safety margin is too small, safety cannot be guaranteed. Therefore, the value of the thermal safety margin should ensure that the second and third target saturation points meet the conditions described in this embodiment to avoid problems caused by excessively large or small thermal safety margins.
[0063] Furthermore, when the unit is in natural circulation, measurement errors in the primary loop pressure and core outlet temperature should not lead to the loss of the undercooling boundary. However, under low pressure, the primary loop temperature limit is highly sensitive to changes in the pressure limit, and the measurement error of the undercooling margin is relatively large. To eliminate this error, the primary loop undersaturation limit line needs to be processed. The processing method can be: obtaining the temperature measurement channel error and the pressure measurement channel error, and processing the primary loop undersaturation limit line based on these errors. For specific processing methods, please refer to [link to relevant documentation]. Figure 5 .
[0064] exist Figure 5In the diagram, the rightmost solid line represents the water saturation curve, and the leftmost solid line represents the initial primary loop undersaturation limit line determined based on the thermal safety margin and the water saturation curve. The initial primary loop undersaturation limit line is shifted horizontally and vertically; the horizontal shift is determined by the temperature measurement channel error, and the vertical shift by the pressure measurement channel error. The resulting curve is the modified primary loop undersaturation limit line. The difference between the modified primary loop undersaturation limit line and the water saturation curve along the horizontal direction is the subcooling margin ΔT. min Under low pressure, ΔT min There may be cases where the supercooling margin is too small or even negative. Therefore, it is necessary to correct the supercooling margin in such cases to a fixed supercooling margin to ensure that the supercooling boundary is not less than the supercooling margin.
[0065] In this embodiment, by establishing a first operating boundary, it is possible to detect whether abnormal operation will occur during the operation of the primary loop due to excessively high coolant temperature.
[0066] Optionally, the first equipment parameter includes the strength of the U-tube sheet of the steam generator. Step 103, based on the first equipment parameter and the first information, determines the second operating boundary, including:
[0067] The pressure limit value of the steam generator is determined based on the strength of the U-shaped tube sheet;
[0068] Based on the pressure limit value, the pressure values of the plurality of saturation points are updated to obtain a plurality of updated second saturation points, wherein the pressure value obtained by adding the pressure limit value to the pressure value of the saturation point before the update is the same as the pressure value corresponding to the updated second saturation point.
[0069] The second operating boundary is determined based on the multiple updated second saturation points;
[0070] The second operating boundary includes: when the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the fourth target saturation point is any one of the plurality of updated second saturation points.
[0071] When the primary loop of a nuclear power unit is in natural circulation mode, it can be approximately assumed that the temperature of the primary loop cold pipe section is roughly equal to that of the secondary side of the steam generator, and the secondary side of the steam generator is in a saturated state, with the saturation temperature depending on the steam generator pressure. Similar to step 103, after determining the pressure limit value, the water saturation curve is shifted upwards based on the pressure limit value to obtain the pressure difference limit line between the primary and secondary sides of the steam generator. The second operating boundary is defined as follows: the average pressure and average temperature are below the pressure difference limit line between the primary and secondary sides of the steam generator. In this embodiment, by establishing the second operating boundary, any abnormalities in the steam generator during primary loop operation can be detected.
[0072] Optionally, the primary loop further includes a cold pipe section and a hot pipe section, and the primary loop includes a zero-temperature-difference state and a maximum-temperature-difference state, wherein, in the zero-temperature-difference state, the temperature of the coolant in the cold pipe section is the same as the temperature of the coolant in the hot pipe section; in the maximum-temperature-difference state, the temperature difference between the temperature of the coolant in the cold pipe section and the temperature of the coolant in the hot pipe section is the maximum expected temperature difference;
[0073] After determining the second operating boundary based on the plurality of updated second saturation points, the method further includes:
[0074] Based on the maximum expected temperature difference, the temperature values of the multiple updated second saturation points are updated to obtain multiple updated third saturation points, wherein the temperature value obtained by adding the maximum expected temperature difference to the temperature value of the multiple updated second saturation points is the same as the temperature value corresponding to the updated third saturation point.
[0075] When the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the average pressure is greater than the pressure corresponding to the fifth target saturation point, the primary side pressure of the steam generator is detected, wherein the fifth target saturation point is the saturation point whose temperature is the same as the temperature corresponding to the fourth target saturation point among the plurality of updated third saturation points;
[0076] An alarm message is generated when the average temperature is the same as the temperature corresponding to the fourth target saturation point, and the primary side pressure is greater than the pressure corresponding to the fourth target saturation point.
[0077] like Figure 6As shown, the top straight line represents the highest pressure of the primary loop. The curve on the left represents the pressure difference limit line between the primary and secondary sides of the steam generator when there is no temperature difference between the cold and hot pipe sections (determined based on multiple updated second saturation points). The curve on the right represents the pressure difference limit line between the primary and secondary sides of the steam generator when there is a maximum temperature difference between the cold and hot pipe sections (determined based on multiple updated third saturation points). It should be noted that under natural circulation conditions, the temperature difference between the hot and cold pipe sections varies due to various factors. Therefore, based on the ranges determined by the two pressure difference limit lines between the primary and secondary sides of the steam generator corresponding to the two extreme cases of no temperature difference between the cold and hot pipe sections and the maximum temperature difference between the cold and hot pipe sections, the operating status of the primary loop can be determined according to the two pressure difference limit lines of the steam generator regardless of the temperature difference.
[0078] Specifically, such as Figure 3 The display shows two curves: one for the pressure difference limit between the primary and secondary sides of the steam generator under conditions of no temperature difference in the hot pipe section, and the other for conditions of maximum temperature difference between the cold and hot pipe sections. When the average pressure and average temperature are between the pressure difference limit lines for the primary and secondary sides of the steam generator under conditions of no temperature difference in the cold and hot pipe sections and maximum temperature difference in the cold and hot pipe sections, the primary side pressure of the steam generator is further monitored. This avoids situations where the average pressure is lower than the pressure difference limit line for the primary and secondary sides of the steam generator under conditions of no temperature difference in the cold and hot pipe sections, but the primary side pressure actually exceeds the pressure limit. This prevents misjudgments of the operating status under the natural circulation of the primary loop and improves the accuracy of the condition monitoring results.
[0079] Optionally, the second equipment parameters include the voltage regulator surge tube strength and the voltage regulator annihilation chamber temperature. Step 105, determining the third operating boundary based on the second equipment parameters and the first information includes:
[0080] The temperature limit value of the voltage regulator is determined based on the voltage regulator oscillation tube strength and the voltage regulator annihilation chamber temperature.
[0081] Based on the temperature limit value, the temperature values of the multiple saturation points are updated to obtain multiple updated fourth saturation points. The temperature value obtained by subtracting the temperature limit value from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated fourth saturation point.
[0082] The third operating boundary is determined based on the multiple updated fourth saturation points;
[0083] The third operating boundary includes: when the average pressure is the same as the pressure corresponding to the sixth target saturation point, the average temperature is greater than the temperature corresponding to the sixth target saturation point, and the sixth target saturation point is any one of the plurality of updated fourth saturation points.
[0084] The voltage regulator is connected to the primary circuit hot section via a surge tube, so the voltage regulator pressure represents the primary circuit pressure. When the coolant in the primary circuit is undersaturated, its temperature is lower than the temperature of the saturated water in the voltage regulator. Therefore, the connection point between the surge tube and the primary circuit hot section experiences a lower temperature. This temperature difference causes thermal stress in the surge tube. To prevent this thermal stress from exceeding the voltage regulator's surge tube strength and damaging it, the temperature difference between the saturated water and the coolant in the voltage regulator must be limited.
[0085] In addition to the strength of the pressurizer surge tube, the temperature difference between the two ends of the surge tube must also meet the temperature required for the nuclear power unit shutdown process, which is used for the pressurizer annihilation chamber.
[0086] Taking into account the limitations imposed on the voltage regulator by the strength of the voltage regulator's oscillating tube and the temperature of the voltage regulator's annihilation chamber, the temperature limit value of the voltage regulator is obtained.
[0087] Similar to steps 103 and 104 above, based on the temperature limit value, the water saturation curve is shifted to the left to obtain the temperature difference limit line at both ends of the regulator's oscillating tube. The third operating boundary is: the average pressure and average temperature are to the right of the temperature difference limit line at both ends of the regulator's oscillating tube. Figure 3 As shown, curve 3 is a temperature difference limit line at both ends of a voltage regulator's oscillating tube.
[0088] In this embodiment, by determining the third operating boundary, it is possible to detect whether there is any abnormality in the voltage regulator during the operation of the primary loop.
[0089] Optionally, the first equipment parameter includes: the safe opening temperature of the steam generator safety valve; the second equipment parameter includes: the second set pressure of the pressure regulator safety valve; and the third equipment parameter includes: the minimum inlet temperature of the waste heat removal system. To ensure the safe operation of the steam generator safety valve, the pressure regulator safety valve, and the waste heat removal system, the temperature or pressure of the coolant needs to meet the above-mentioned limitations. It should be noted that the waste heat removal system is also used for heat exchange, but it replaces the steam generator for heat exchange. The steam generator is used when the temperature is high, and the waste heat removal system is used as the temperature decreases. When the waste heat removal system is used for heat exchange, the waste heat removal system safety valve provides overpressure protection for the primary circuit. When the waste heat removal system stops working or is disconnected, the pressure regulator safety valve provides overpressure protection for the primary circuit. The protection setting of the pressure regulator safety valve is less than the pressure regulator pressure corresponding to the allowable pressure of the pressure vessel in the waste heat discharge system at the lowest access temperature. This allows the minimum access temperature to be determined. It should be noted that before reaching the minimum access temperature, the heat exchange needs to be switched from the steam generator to the waste heat discharge system.
[0090] The target operating boundary of the coolant includes at least the following: the average pressure is less than or equal to the second set pressure, the average temperature is less than the safe opening temperature, and the average pressure is located within the first operating boundary, the second operating boundary, and the third operating boundary when the average temperature is greater than or equal to the minimum access temperature.
[0091] Please refer to the above. Figure 3 Curve 8 represents the limit line corresponding to the safe opening temperature of the steam generator safety valve, and curve 10 represents the limit line corresponding to the second set pressure of the pressure regulator safety valve (in...). Figure 3 In the illustrated embodiment, the voltage regulator has three safety valves, thus having three limit lines. Curve 5 is the limit line corresponding to the lowest inlet temperature of the waste heat removal system. The target operating boundary is defined as the area enclosed by curves 2, 3, 4, 5, 8, and 10, where the average pressure and average temperature are located below curve 10, to the left of curve 8, to the right of curve 5, to the right of curve 3, below curve 4, and to the left of curve 2.
[0092] In this embodiment, a target operating boundary is pre-established. When monitoring the primary loop status, only the average temperature and average pressure of the coolant need to be detected. The operation of the primary loop is determined by whether the average temperature and average pressure are within the target operating boundary. The operation is simple and quick.
[0093] Optionally, the third equipment parameter also includes the maximum limiting pressure of the waste heat removal system. The target operating boundary further includes: when the average temperature is less than the minimum inlet temperature, the average pressure is less than the maximum limiting pressure, the average temperature is greater than the minimum coolant temperature, and the average pressure and average temperature are within the first operating boundary.
[0094] Please see further. Figure 3 Curve 6 represents the limit line corresponding to the maximum limiting pressure of the waste heat removal system. The higher the maximum limiting pressure of the waste heat removal system, the higher the saturated water temperature inside the regulator in two-phase operation, and the higher the corresponding primary loop operating temperature given a fixed temperature difference limit across the oscillating tube. To ensure sufficient temperature range for annihilation chamber operation when the waste heat removal system is functioning, the maximum limiting pressure for its connection must be limited. Curve 7 represents the limit line corresponding to the minimum coolant temperature. When the average coolant temperature is lower than the minimum connection temperature, the waste heat removal system needs to be connected for operation. Therefore, the average pressure needs to be lower than the maximum limiting temperature; that is, the average temperature and average pressure are to the right of curve 7, below curve 6, and to the left of curve 5. This embodiment considers the case of the waste heat removal system operating in the primary loop, further improving the comprehensiveness of the condition monitoring method in this embodiment.
[0095] Optionally, the primary loop further includes a nuclear reactor, and after determining the target operating boundary of the coolant based on the first operating boundary, the second operating boundary, the third operating boundary, the first equipment parameters, the second equipment parameters, and the third equipment parameters, the method further includes:
[0096] Obtain the maximum permissible temperature of the coolant in the core of the nuclear reactor;
[0097] When the average temperature is greater than the safe opening temperature and less than the maximum allowable temperature of the coolant, the real-time outlet temperature of the nuclear reactor core is detected.
[0098] An alarm message is generated if the real-time outlet temperature exceeds the maximum allowable temperature of the coolant.
[0099] Please refer to the above. Figure 3 , Figure 3 Curve 9 represents the limit line corresponding to the maximum allowable temperature of the coolant in the nuclear reactor core. When the average temperature and average pressure of the coolant are between curves 8 and 9, it is necessary to further monitor the real-time outlet temperature of the nuclear reactor core to avoid the inability to detect operational anomalies caused by the real-time outlet temperature exceeding the maximum allowable temperature of the coolant, thus further improving the comprehensiveness and accuracy of the monitoring method in this embodiment.
[0100] like Figure 7 As shown in the illustration, this application also provides a condition monitoring device for the primary loop of a nuclear power unit. The condition monitoring device 700 for the primary loop of a nuclear power unit includes:
[0101] The acquisition module 701 is used to acquire the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, and the third equipment parameters of the waste heat removal system when the first loop is in a natural circulation state, and to acquire first information, the first information including the temperature and pressure saturation set of the coolant in the first loop, the temperature and pressure saturation set including the temperature value of the coolant in a saturated state under the pressure value corresponding to each saturation point at multiple saturation points.
[0102] The detection module 702 is used to detect the average temperature and average pressure of the coolant, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time.
[0103] The first determining module 703 is used to determine the first operating boundary based on the thermal safety margin of the first loop and the first information;
[0104] The second determining module 704 is used to determine the second operating boundary based on the first device parameters and the first information;
[0105] The third determining module 705 is used to determine the third operating boundary based on the second device parameters and the first information;
[0106] The fourth determining module 706 is used to determine the target operating boundary of the coolant based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
[0107] Optionally, the first determining module 703 is further configured to:
[0108] Based on the thermal safety margin, the temperature values of the multiple saturation points are updated to obtain multiple updated first saturation points. The temperature value obtained by subtracting the thermal safety margin from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated first saturation point.
[0109] The first operating boundary is determined based on the multiple updated first saturation points;
[0110] Wherein, the first operating boundary includes: when the average pressure is the same as the pressure corresponding to the first target saturation point, the average temperature is less than the temperature corresponding to the first target saturation point, and the first target saturation point is any one of the plurality of updated first saturation points.
[0111] Optionally, the temperature of the second target saturation point is greater than or equal to the hot zero-power temperature of the coolant, and the pressure of the third target saturation point is less than or equal to the hot zero-power pressure of the coolant.
[0112] Wherein, the second target saturation point is the saturation point in the plurality of updated first saturation points whose pressure is the same as the thermal zero-power pressure, and the third target saturation point is the saturation point in the plurality of updated first saturation points whose temperature is the same as the thermal zero-power temperature.
[0113] Optionally, the first equipment parameters include the strength of the U-tube sheet of the steam generator, and the second determining module 704 is further used for:
[0114] The pressure limit value of the steam generator is determined based on the strength of the U-shaped tube sheet;
[0115] Based on the pressure limit value, the pressure values of the plurality of saturation points are updated to obtain a plurality of updated second saturation points, wherein the pressure value obtained by adding the pressure limit value to the pressure value of the saturation point before the update is the same as the pressure value corresponding to the updated second saturation point.
[0116] The second operating boundary is determined based on the multiple updated second saturation points;
[0117] The second operating boundary includes: when the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the fourth target saturation point is any one of the plurality of updated second saturation points.
[0118] Optionally, the primary loop further includes a cold pipe section and a hot pipe section. The primary loop includes a zero-temperature-difference state and a maximum-temperature-difference state. In the zero-temperature-difference state, the temperature of the coolant in the cold pipe section and the temperature of the coolant in the hot pipe section are the same. In the maximum-temperature-difference state, the temperature difference between the coolant in the cold pipe section and the coolant in the hot pipe section is the maximum expected temperature difference. The nuclear power unit primary loop condition monitoring device 700 is also used for:
[0119] Based on the maximum expected temperature difference, the temperature values of the multiple updated second saturation points are updated to obtain multiple updated third saturation points, wherein the temperature value obtained by adding the maximum expected temperature difference to the temperature value of the multiple updated second saturation points is the same as the temperature value corresponding to the updated third saturation point.
[0120] When the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the average pressure is greater than the pressure corresponding to the fifth target saturation point, the primary side pressure of the steam generator is detected, wherein the fifth target saturation point is the saturation point whose temperature is the same as the temperature corresponding to the fourth target saturation point among the plurality of updated third saturation points;
[0121] An alarm message is generated when the average temperature is the same as the temperature corresponding to the fourth target saturation point, and the primary side pressure is greater than the pressure corresponding to the fourth target saturation point.
[0122] Optionally, the second device parameters include the voltage regulator surge tube strength and the voltage regulator annihilation chamber temperature, and the third determining module 705 is further used for:
[0123] The step of determining the third operating boundary based on the second device parameters and the first information includes:
[0124] The temperature limit value of the voltage regulator is determined based on the voltage regulator oscillation tube strength and the voltage regulator annihilation chamber temperature.
[0125] Based on the temperature limit value, the temperature values of the multiple saturation points are updated to obtain multiple updated fourth saturation points. The temperature value obtained by subtracting the temperature limit value from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated fourth saturation point.
[0126] The third operating boundary is determined based on the multiple updated fourth saturation points;
[0127] The third operating boundary includes: when the average pressure is the same as the pressure corresponding to the sixth target saturation point, the average temperature is greater than the temperature corresponding to the sixth target saturation point, and the sixth target saturation point is any one of the plurality of updated fourth saturation points.
[0128] Optionally, the first equipment parameter includes: the safe opening temperature of the steam generator safety valve; the second equipment parameter includes: the second set pressure of the pressure regulator safety valve; and the third equipment parameter includes: the minimum access temperature of the waste heat discharge system.
[0129] The target operating boundary of the coolant includes at least the following: the average pressure is less than or equal to the second set pressure, the average temperature is less than the safe opening temperature, and the average pressure is located within the first operating boundary, the second operating boundary, and the third operating boundary when the average temperature is greater than or equal to the minimum access temperature.
[0130] Optionally, the third equipment parameter may also include the maximum limiting pressure of the waste heat removal system;
[0131] The target operating boundary further includes: when the average temperature is less than the minimum access temperature, the average pressure is less than the maximum limit pressure, the average temperature is greater than the minimum coolant temperature and the average pressure, and the average temperature is within the first operating boundary.
[0132] Optionally, the primary loop further includes a nuclear reactor, and the condition monitoring device 700 for the primary loop of the nuclear power unit is also used for:
[0133] Obtain the maximum permissible temperature of the coolant in the core of the nuclear reactor;
[0134] When the average temperature is greater than the safe opening temperature and less than the maximum allowable temperature of the coolant, the real-time outlet temperature of the nuclear reactor core is detected.
[0135] An alarm message is generated if the real-time outlet temperature exceeds the maximum allowable temperature of the coolant.
[0136] It should be noted that the nuclear power unit primary loop condition monitoring device 700 provided in this application embodiment can achieve the following: Figure 1 The entire technical process of the nuclear power unit primary loop condition monitoring method shown in the embodiment, and achieving the same technical effect, will not be repeated here to avoid repetition.
[0137] This application also provides an electronic device, including: a processor, a memory, and a program stored in the memory and executable on the processor, wherein the program, when executed by the processor, implements the above-described functionality. Figure 1 The various processes of the method embodiments shown can achieve the same technical effect, and will not be described again here to avoid repetition.
[0138] For details, see Figure 8 As shown in the figure, this application embodiment also provides an electronic device, including a bus 801, a transceiver 802, an antenna 803, a bus interface 804, a processor 805, and a memory 806.
[0139] In this embodiment, the electronic device further includes: a computer program stored in memory 806 and executable on processor 805; the computer program, when executed by processor 805, can perform the following functions: Figure 1 The various processes of the nuclear power unit primary loop condition monitoring method shown in the embodiment can achieve the same technical effect, and will not be described again here to avoid repetition.
[0140] exist Figure 8 In this document, a bus architecture (represented by bus 801) is used. Bus 801 can include any number of interconnected buses and bridges, linking various circuits including one or more processors represented by processor 805 and memory represented by memory 806. Bus 801 can also link various other circuits such as peripheral devices, voltage regulators, and power management circuits, which are well known in the art and therefore will not be described further herein. Bus interface 804 provides an interface between bus 801 and transceiver 802. Transceiver 802 can be a single element or multiple elements, such as multiple receivers and transmitters, providing a unit for communicating with various other devices over a transmission medium. Data processed by processor 805 is transmitted over a wireless medium via antenna 803, which further receives data and transmits data to processor 805.
[0141] The processor 805 manages the bus 801 and handles general processing, and also provides various functions, including timing, peripheral interfaces, voltage regulation, power management, and other control functions. The memory 806 can be used to store data used by the processor 805 during operation.
[0142] Optionally, the processor 805 can be a CPU, ASIC, FPGA, or CPLD.
[0143] This application also provides a computer-readable storage medium storing a computer program. When executed by a processor, this computer program implements the various processes of the above-described nuclear power unit primary loop state monitoring method embodiment and achieves the same technical effect. To avoid repetition, it will not be described again here. The computer-readable storage medium may be, for example, ROM, RAM, magnetic disk, or optical disk.
[0144] This application also provides a computer program product, including computer instructions, which, when executed by a processor, implement the above-described... Figure 1 The various processes of the embodiment of the state monitoring method for the primary loop of the nuclear power unit shown are all applicable and can achieve the same technical effect. To avoid repetition, they will not be described again here.
[0145] It should be noted that, in this document, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Unless otherwise specified, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes that element.
[0146] Through the above description of the embodiments, those skilled in the art can clearly understand that the methods of the above embodiments can be implemented by means of software plus necessary general-purpose hardware platforms. Of course, they can also be implemented by hardware, but in many cases the former is a better implementation method. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a software product. This computer software product is stored in a storage medium (such as ROM / RAM, magnetic disk, optical disk) and includes several instructions to cause a terminal (which may be a mobile phone, computer, server, air conditioner, or network device, etc.) to execute the methods described in the various embodiments of this application.
[0147] The embodiments of this application have been described above with reference to the accompanying drawings. However, this application is not limited to the specific embodiments described above. The specific embodiments described above are merely illustrative and not restrictive. Those skilled in the art can make many other forms under the guidance of this application without departing from the spirit and scope of the claims, and all of these forms are within the protection scope of this application.
Claims
1. A method for condition monitoring of the primary loop of a nuclear power unit, characterized in that, The primary loop includes a steam generator, a pressure regulator, and a waste heat removal system; the method includes: When the first loop is in a natural circulation state, the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, the third equipment parameters of the waste heat removal system, and the first information are obtained. The first information includes the temperature and pressure saturation set of the coolant in the first loop. The temperature and pressure saturation set includes the temperature value of the coolant in a saturated state at the pressure value corresponding to each saturation point under multiple saturation points. The average temperature and average pressure of the coolant are detected, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time. Based on the thermal safety margin of the first loop and the first information, the first operating boundary is determined; Based on the first device parameters and the first information, the second operating boundary is determined; Based on the second device parameters and the first information, the third operating boundary is determined; Based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, the target operating boundary of the coolant is determined, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
2. The method as described in claim 1, characterized in that, The determination of the first operating boundary based on the thermal safety margin of the first loop and the first information includes: Based on the thermal safety margin, the temperature values of the multiple saturation points are updated to obtain multiple updated first saturation points. The temperature value obtained by subtracting the thermal safety margin from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated first saturation point. The first operating boundary is determined based on the multiple updated first saturation points; Wherein, the first operating boundary includes: when the average pressure is the same as the pressure corresponding to the first target saturation point, the average temperature is less than the temperature corresponding to the first target saturation point, and the first target saturation point is any one of the plurality of updated first saturation points.
3. The method as described in claim 2, characterized in that, The temperature of the second target saturation point is greater than or equal to the hot zero-power temperature of the coolant, and the pressure of the third target saturation point is less than or equal to the hot zero-power pressure of the coolant. Wherein, the second target saturation point is the saturation point in the plurality of updated first saturation points whose pressure is the same as the thermal zero-power pressure, and the third target saturation point is the saturation point in the plurality of updated first saturation points whose temperature is the same as the thermal zero-power temperature.
4. The method as described in claim 1, characterized in that, The first equipment parameter includes the strength of the U-tube sheet of the steam generator; Determining the second operating boundary based on the first device parameters and the first information includes: The pressure limit value of the steam generator is determined based on the strength of the U-shaped tube sheet; Based on the pressure limit value, the pressure values of the plurality of saturation points are updated to obtain a plurality of updated second saturation points, wherein the pressure value obtained by adding the pressure limit value to the pressure value of the saturation point before the update is the same as the pressure value corresponding to the updated second saturation point. The second operating boundary is determined based on the multiple updated second saturation points; The second operating boundary includes: when the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the fourth target saturation point is any one of the plurality of updated second saturation points.
5. The method as described in claim 4, characterized in that, The primary loop further includes a cold pipe section and a hot pipe section. The primary loop includes a zero-temperature-difference state and a maximum-temperature-difference state. In the zero-temperature-difference state, the temperature of the coolant in the cold pipe section is the same as the temperature of the coolant in the hot pipe section. In the maximum-temperature-difference state, the temperature difference between the coolant in the cold pipe section and the coolant in the hot pipe section is the maximum expected temperature difference. After determining the second operating boundary based on the plurality of updated second saturation points, the method further includes: Based on the maximum expected temperature difference, the temperature values of the multiple updated second saturation points are updated to obtain multiple updated third saturation points, wherein the temperature value obtained by adding the maximum expected temperature difference to the temperature value of the multiple updated second saturation points is the same as the temperature value corresponding to the updated third saturation point. When the average temperature is the same as the temperature corresponding to the fourth target saturation point, the average pressure is less than the pressure corresponding to the fourth target saturation point, and the average pressure is greater than the pressure corresponding to the fifth target saturation point, the primary side pressure of the steam generator is detected, wherein the fifth target saturation point is the saturation point whose temperature is the same as the temperature corresponding to the fourth target saturation point among the plurality of updated third saturation points; An alarm message is generated when the average temperature is the same as the temperature corresponding to the fourth target saturation point, and the primary side pressure is greater than the pressure corresponding to the fourth target saturation point.
6. The method as described in claim 1, characterized in that, The second equipment parameters include the voltage regulator surge tube strength and the voltage regulator annihilation chamber temperature; The step of determining the third operating boundary based on the second device parameters and the first information includes: The temperature limit value of the voltage regulator is determined based on the voltage regulator oscillation tube strength and the voltage regulator annihilation chamber temperature. Based on the temperature limit value, the temperature values of the multiple saturation points are updated to obtain multiple updated fourth saturation points. The temperature value obtained by subtracting the temperature limit value from the temperature value of the saturation point before the update is the same as the temperature value corresponding to the updated fourth saturation point. The third operating boundary is determined based on the multiple updated fourth saturation points; The third operating boundary includes: when the average pressure is the same as the pressure corresponding to the sixth target saturation point, the average temperature is greater than the temperature corresponding to the sixth target saturation point, and the sixth target saturation point is any one of the plurality of updated fourth saturation points.
7. The method according to any one of claims 1 to 6, characterized in that, The first equipment parameter includes: the safe opening temperature of the steam generator safety valve; the second equipment parameter includes: the second set pressure of the pressure regulator safety valve; and the third equipment parameter includes: the minimum access temperature of the waste heat discharge system. The target operating boundary of the coolant includes at least the following: the average pressure is less than or equal to the second set pressure, the average temperature is less than the safe opening temperature, and the average pressure is located within the first operating boundary, the second operating boundary, and the third operating boundary when the average temperature is greater than or equal to the minimum access temperature.
8. The method as described in claim 7, characterized in that, The third equipment parameter also includes the maximum limiting pressure of the waste heat removal system; The target operating boundary further includes: when the average temperature is less than the minimum access temperature, the average pressure is less than the maximum limit pressure, the average temperature is greater than the minimum coolant temperature and the average pressure, and the average temperature is within the first operating boundary.
9. The method as described in claim 8, characterized in that, The primary loop further includes a nuclear reactor. After determining the target operating boundary of the coolant based on the first operating boundary, the second operating boundary, the third operating boundary, the first equipment parameters, the second equipment parameters, and the third equipment parameters, the method further includes: Obtain the maximum permissible temperature of the coolant in the core of the nuclear reactor; When the average temperature is greater than the safe opening temperature and less than the maximum allowable temperature of the coolant, the real-time outlet temperature of the nuclear reactor core is detected. An alarm message is generated if the real-time outlet temperature exceeds the maximum allowable temperature of the coolant.
10. A condition monitoring device for the primary loop of a nuclear power unit, characterized in that, The primary circuit includes a steam generator, a pressure regulator, and a waste heat removal system; the device includes: The acquisition module is used to acquire the first equipment parameters of the steam generator, the second equipment parameters of the pressure regulator, and the third equipment parameters of the waste heat removal system when the first loop is in a natural circulation state, and to acquire first information, the first information including the temperature and pressure saturation set of the coolant in the first loop, the temperature and pressure saturation set including the temperature value of the coolant in a saturated state at the pressure value corresponding to each saturation point under multiple saturation points. The detection module is used to detect the average temperature and average pressure of the coolant, wherein the average temperature is the average temperature at all points in the primary circuit at the same time, and the average pressure is the average pressure at all points in the primary circuit at the same time. The first determining module is used to determine the first operating boundary based on the thermal safety margin of the first loop and the first information; The second determining module is used to determine the second operating boundary based on the first device parameters and the first information; The third determining module is used to determine the third operating boundary based on the second device parameters and the first information; The fourth determining module is used to determine the target operating boundary of the coolant based on the first operating boundary, the second operating boundary, the third operating boundary, the first device parameter, the second device parameter, and the third device parameter, wherein the first operating boundary, the second operating boundary, the third operating boundary, and the target operating boundary are all used to limit the average temperature and the average pressure.
11. An electronic device, characterized in that, include: A processor, a memory, and a program stored in the memory and executable on the processor, wherein the program, when executed by the processor, implements the steps of the state monitoring method for the primary loop of a nuclear power unit as described in any one of claims 1 to 9.
12. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores a computer program that, when executed by a processor, implements the steps of the state monitoring method for the primary loop of a nuclear power unit as described in any one of claims 1 to 9.
13. A computer program product, characterized in that, It includes computer instructions, which, when executed by a processor, implement the steps of the state monitoring method for the primary loop of a nuclear power unit as described in any one of claims 1 to 9.