Method and system for performance testing of a nuclear reactor coolant pump

Abstract

The embodiment of the application discloses a kind of performance test method and system of nuclear reactor coolant pump, it is related to nuclear reactor technical field, method includes: obtaining the first measurement sequence of main pump in nuclear reactor under the condition of power failure, and the second measurement value of main pump under the condition of power failure moment, first measurement sequence includes multiple first measurement values;According to first measurement sequence and second measurement value, determine the initial drop curve of coolant flow in primary loop;According to initial drop curve, and the coolant steady flow of each coolant loop in primary loop under different power of nuclear reactor, determine target drop curve;According to target drop curve, first preset coasting flow curve and second preset coasting flow curve, determine whether the performance test result of main pump meets the safety analysis requirement, can improve the accuracy of main pump coasting performance test.

Description

Technical Field

[0001] This application relates to the field of nuclear reactor technology, and in particular to a performance testing method and system for a nuclear reactor coolant pump. Background Technology

[0002] Coolant pumps in nuclear reactors are critical equipment for ensuring coolant circulation in the reactor core, and their coasting performance directly affects the ability to remove residual heat from the core after shutdown. However, current acceptance criteria and strategies for coolant pump coasting tests are incomplete in their assessment of coolant pump coasting performance, leading to low accuracy in these tests and an inability to reflect whether the actual coasting performance of the coolant pump meets the requirements of safety analysis. Summary of the Invention

[0003] In view of this, one of the objectives of this application is to provide a performance testing method and system for nuclear reactor coolant pumps, which can improve the accuracy of the coasting performance test of the main pump.

[0004] To achieve the above objectives, the technical solution of this application is implemented as follows:

[0005] In a first aspect, embodiments of this application provide a performance testing method for a nuclear reactor coolant pump, the method comprising:

[0006] The sequence of first measurement values ​​of the main pump in the nuclear reactor after power failure and the second measurement value of the main pump at the moment of power failure are obtained. The sequence of first measurement values ​​includes multiple first measurement values. The main pump is the coolant pump in the nuclear reactor.

[0007] Based on the first measurement sequence and the second measurement, determine the initial decrease curve of the coolant flow rate in the primary loop;

[0008] Based on the initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels, the target descent curve is determined.

[0009] Based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, the performance test results of the main pump are determined. The first preset coasting flow rate curve and the second preset coasting flow rate curve are obtained based on the preset safety analysis results. The first preset coasting flow rate curve and the second preset coasting flow rate curve are used to indicate whether the performance test results meet the safety analysis requirements.

[0010] In one possible implementation, the first measurement value is the measurement value of the coolant flow rate in the first circuit after power failure, and the second measurement value is the measurement value of the coolant flow rate in the first circuit at the instant of power failure.

[0011] Alternatively, the first measurement value is the speed measurement value of the main pump after power failure, and the second measurement value is the speed measurement value of the main pump at the instant of power failure.

[0012] In one possible implementation, the initial descent curve includes sub-descent curves corresponding to each coolant loop in a primary loop;

[0013] Based on the initial descent curve and the steady-state coolant flow rates in each coolant loop of the first loop during reactor operation at different power levels, the target descent curve is determined, including:

[0014] Based on the heat balance method, determine the absolute value of the steady-state flow rate and the value of the flow rate uncertainty of each coolant loop;

[0015] The target descent curve is determined based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor.

[0016] In one possible implementation, after determining the initial decrease curve of the coolant flow rate in the primary loop based on the first measurement sequence and the second measurement, the method further includes:

[0017] Obtain the response time of detectors in a nuclear reactor;

[0018] The initial descent curve is updated based on the detector response time to obtain the updated initial descent curve;

[0019] Based on the initial descent curve and the steady-state coolant flow rates in each coolant loop of the first loop during reactor operation at different power levels, the target descent curve is determined, including:

[0020] The target descent curve is determined based on the updated initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels.

[0021] In one possible implementation, the target descent curve includes a first target descent curve, and the design flow rate includes the thermal design flow rate.

[0022] Based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor, the target descent curve is determined, including:

[0023] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0024] Based on all intermediate descent curves, flow uncertainty values, and thermal design flow rates, the first target descent curve is determined.

[0025] In one possible implementation, the target descent curve includes a second target descent curve, and the design flow rate includes the mechanical design flow rate;

[0026] Based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor, the target descent curve is determined, including:

[0027] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0028] The second target descent curve is determined based on all intermediate descent curves, flow uncertainty values, and mechanical design flow rates.

[0029] In one possible implementation, the performance test results of the main pump are determined based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, including:

[0030] If, at the same time point, the value of the first target decline curve is greater than the value corresponding to the first preset idle flow curve, and the value of the second target decline curve is less than the value corresponding to the second preset idle flow curve, then the performance test result is deemed qualified.

[0031] In one possible implementation, before determining the performance test results of the main pump based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, the method further includes:

[0032] Obtain the range of the first assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0033] Based on the uncertainty parameter range of the first assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events in the nuclear reactor under the design reference condition, the occurrence frequency of each transient event, and the deviation nucleus boiling risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0034] Based on the frequency of occurrence of each transient event and the deviation from the boiling risk value corresponding to each transient event, the first target transient event is determined from multiple transient events, and the operating condition corresponding to the first target transient event is the first target operating condition;

[0035] When the deviation from nucleation boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold, the range of the first initial uncertainty parameter is determined.

[0036] Based on the first initial uncertainty parameter range, the first preset working condition is simulated to obtain the first target uncertainty parameter range;

[0037] Based on the uncertainty parameter range of the first objective, the first objective operating condition is simulated to obtain the first preset coasting flow curve.

[0038] In one possible implementation, before determining the performance test results of the main pump based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, the method further includes:

[0039] Obtain the range of the second assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0040] Based on the uncertainty parameter range of the second assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events corresponding to the load conditions in the nuclear reactor, the occurrence frequency of each transient event, and the overpressure risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0041] Based on the frequency of occurrence of each transient event and the overpressure risk value corresponding to each transient event, a second target transient event is determined from multiple transient events, and the operating condition corresponding to the second target transient event is the second target operating condition;

[0042] If the overpressure risk value corresponding to the second target working condition is less than the second preset safety threshold, determine the range of the second initial uncertainty parameter.

[0043] Based on the second initial uncertainty parameter range, the second preset working condition is simulated to obtain the second target uncertainty parameter range;

[0044] Based on the uncertainty parameter range of the second objective, the second objective operating condition is simulated to obtain the second preset coasting flow curve.

[0045] Secondly, embodiments of this application provide a performance testing system for a nuclear reactor coolant pump, the system comprising:

[0046] The acquisition module is used to acquire the first measurement value sequence of the main pump in the nuclear reactor after power failure, and the second measurement value of the main pump at the moment of power failure. The first measurement value sequence includes multiple first measurement values. The main pump is the coolant pump in the nuclear reactor.

[0047] The first determining module is used to determine the initial decreasing curve of the coolant flow rate in the primary loop based on the first measurement value sequence and the second measurement value.

[0048] The second determining module is used to determine the target descent curve based on the initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels.

[0049] The third determining module is used to determine the performance test results of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve. The first preset coasting flow curve and the second preset coasting flow curve are obtained based on the preset safety analysis results. The first preset coasting flow curve and the second preset coasting flow curve are used to indicate whether the performance test results meet the safety analysis requirements.

[0050] The performance testing method for a nuclear reactor coolant pump provided in this application obtains a first measurement sequence of the main pump in the reactor after power failure and a second measurement sequence of the main pump at the instant of power failure, thereby determining the initial decrease curve of the coolant flow rate in the primary loop. Subsequently, based on the initial decrease curve and the steady-state coolant flow rate of each coolant loop in the primary loop under different power operation of the nuclear reactor, a target decrease curve can be determined. Finally, based on the target decrease curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, it can be determined whether the performance test results of the main pump meet the safety analysis requirements, thereby improving the accuracy of the main pump coasting performance test. Attached Figure Description

[0051] To more clearly illustrate the technical solutions in the embodiments of this application or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. It should be understood that 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.

[0052] Figure 1 A flowchart illustrating a performance testing method for a nuclear reactor coolant pump, provided as an embodiment of this application;

[0053] Figure 2 A flowchart illustrating the determination of a preset coasting flow rate curve in a performance testing method for a nuclear reactor coolant pump provided in this application embodiment;

[0054] Figure 3 A comparative schematic diagram relating to a performance testing method for a nuclear reactor coolant pump provided in an embodiment of this application;

[0055] Figure 4 Another comparative schematic diagram related to a performance testing method for a nuclear reactor coolant pump provided in an embodiment of this application;

[0056] Figure 5A functional module diagram of a performance testing system for a nuclear reactor coolant pump provided in this application embodiment;

[0057] Figure 6 This is a diagram illustrating the internal structure of an electronic device as provided in an embodiment of this application.

[0058] Explanation of reference numerals in the attached figures:

[0059] 500. Performance testing system for nuclear reactor coolant pumps;

[0060] 510. Acquisition Module;

[0061] 520. First Determined Module;

[0062] 530. Second Determination Module;

[0063] 540. The third determination module. Detailed Implementation

[0064] To make the objectives, technical solutions, and advantages of the embodiments of this application clearer, the technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. The components of the embodiments of this application described and shown in the accompanying drawings can generally be arranged and designed in various different configurations.

[0065] Therefore, the following detailed description of the embodiments of this application provided in the accompanying drawings is not intended to limit the scope of the claimed application, but merely to illustrate selected embodiments of the application. All other embodiments obtained by those skilled in the art based on the embodiments of this application without inventive effort are within the scope of protection of this application.

[0066] It should be noted that similar labels and letters in the following figures indicate similar items. Therefore, once an item is defined in one figure, it does not need to be further defined and explained in subsequent figures.

[0067] In various embodiments of this application, the expression "or" or "at least one of A and / or B" includes any combination or all combinations of the words listed simultaneously. For example, the expression "A or B" or "at least one of A and / or B" may include A, may include B, or may include both A and B.

[0068] In the description of this application, it should be noted that if terms such as "upper," "lower," "inner," or "outer" are used to indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings, or the orientation or positional relationship in which the product of the invention is usually placed during use, they are only for the convenience of describing this application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of this application.

[0069] Furthermore, the terms "first" and "second" are used only to distinguish descriptions and should not be interpreted as indicating or implying relative importance.

[0070] It should be noted that, where there is no conflict, the features in the embodiments of this application can be combined with each other.

[0071] Furthermore, in the embodiments of this application, the term "connection" can refer to "electrical connection" or "direct connection." "Electrical connection" can refer to a direct electrical connection between two components, or it can refer to an electrical connection between two components via one or more normally open tubes or other components.

[0072] To facilitate a better understanding of the solutions in the embodiments of this application, the relevant technologies and corresponding background technologies will be introduced first below.

[0073] The primary loop of a nuclear reactor consists of multiple loops, each equipped with a coolant pump, hereinafter referred to as the "main pump." The main pump drives the coolant to circulate within the Reactor Coolant System (RCP), continuously transferring the heat generated in the reactor core to the secondary feedwater of the steam generator. The main pump must ensure an adequate amount of coolant flows through the reactor core to maintain the Departure from Nucleate Boiling Ratio (DNBR) greater than the design allowable value. In the event of a power failure of the main pump, the nuclear reactor undergoes an emergency shutdown. After shutdown, the remaining power of the nuclear reactor decreases exponentially; therefore, a high coolant flow rate through the reactor core must be maintained for a short period.

[0074] The aforementioned main pump is equipped with a relatively heavy coasting flywheel, which is fixed to the shaft end of the electric motor in the nuclear reactor. This increases the rotational inertia of the main pump and extends its coasting time. The applicant's research revealed that in the event of a main pump power failure and coasting, if the primary coolant level drops too quickly, the remaining heat in the core cannot be carried away by the coolant, potentially causing the fuel rod cladding surface to deviate from nucleate boiling (DNB), thus burning the fuel cladding and compromising the reactor's first safety barrier. If the primary coolant level drops too slowly, resulting in a delayed arrival of shutdown signals such as "low main pump speed" or "low reactor coolant flow," the core remains at a high power level for an extended period, potentially causing overpressure in the primary coolant system. Simultaneously, the high-power core heat is transferred to the secondary coolant system, which may also cause overpressure.

[0075] Coasting tests on the main pumps can be performed during precritical hot shutdowns, when some or all main pumps are simultaneously shut down, to verify whether the coolant flow rate decay in the primary coolant loop meets safety analysis requirements. The corresponding test acceptance criteria can be called safety criteria. As mentioned earlier, excessively rapid coolant decay in the primary coolant loop can easily lead to the DNB phenomenon, while excessively slow coolant decay can easily lead to overpressure in the loop. Therefore, coasting tests on the main pumps are necessary to ensure that the primary coolant flow rate meets the rapid decay criteria and the slow decay criteria, while simultaneously preventing the DNB phenomenon in the reactor core and overpressure in the primary and secondary coolant loops.

[0076] The aforementioned primary loop system generally refers to the RCP. The RCP, also known as the primary loop system, is the reactor coolant system in a nuclear power plant.

[0077] The aforementioned secondary loop system, also known as the steam and energy conversion system, is a secondary coolant circulation system within a nuclear power plant that receives and utilizes the core heat carried out by the reactor coolant (for power generation or heating).

[0078] To improve the accuracy of main pump coasting performance testing, this application provides a performance testing method for a nuclear reactor coolant pump, a performance testing system for a nuclear reactor coolant pump, electronic equipment, a computer-readable storage medium, and a computer program product. The performance testing method for a nuclear reactor coolant pump provided in this application is described below.

[0079] Please see Figure 1 , Figure 1 This is a flowchart illustrating a performance testing method for a nuclear reactor coolant pump, provided as an embodiment of this application. This performance testing method can be applied to the performance testing system or electronic equipment for the nuclear reactor coolant pump described in the following embodiments, wherein the electronic equipment includes personal computers, servers, mobile devices, cloud computing platforms, and supercomputers, etc.

[0080] The following section describes the performance testing method for this nuclear reactor coolant pump, which will be applied to electronic equipment. The method specifically includes the following steps:

[0081] Step 110: Obtain the first measurement value sequence of the main pump in the nuclear reactor after power failure, and the second measurement value of the main pump at the moment of power failure. The first measurement value sequence includes multiple first measurement values. The main pump is the coolant pump in the nuclear reactor.

[0082] Step 120: Determine the initial decrease curve of coolant flow rate in the primary loop based on the first measurement value sequence and the second measurement value.

[0083] Step 130: Determine the target descent curve based on the initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels.

[0084] Step 140: Determine the performance test results of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve. The first preset coasting flow curve and the second preset coasting flow curve are obtained based on the preset safety analysis results. The first preset coasting flow curve and the second preset coasting flow curve are used to indicate whether the performance test results meet the safety analysis requirements.

[0085] The performance testing method for a nuclear reactor coolant pump provided in this application obtains a first measurement sequence of the main pump in the reactor after power failure and a second measurement sequence of the main pump at the instant of power failure, thereby determining the initial decrease curve of the coolant flow rate in the primary loop. Subsequently, based on the initial decrease curve and the steady-state coolant flow rate of each coolant loop in the primary loop under different power operation of the nuclear reactor, a target decrease curve can be determined. Finally, based on the target decrease curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, it can be determined whether the performance test results of the main pump meet the safety analysis requirements, thereby improving the accuracy of the main pump coasting performance test.

[0086] The following will discuss how Figure 1 The steps of the Chinese method are explained in detail.

[0087] In step 110, the electronic device can acquire a first measurement sequence of the main pump in the state after power failure and a second measurement sequence in the state at the moment of power failure. The first measurement sequence and the second measurement sequence can be used to determine the target descent curve in the following embodiments.

[0088] The above-mentioned first measurement sequence can be used to represent the change in coolant flow rate over time in the primary loop when the main pump is powered off.

[0089] The second measurement value mentioned above can be used to represent the coolant flow rate in the primary loop when the main pump is powered off.

[0090] Based on the similarity law of centrifugal pumps, for the same main pump, the ratio of coolant flow rates in the loop is directly proportional to the ratio of the main pump's rotational speed. In one possible implementation, the first measurement value is the coolant flow rate in the first loop after power failure, and the second measurement value is the coolant flow rate in the first loop at the instant of power failure.

[0091] Alternatively, the first measurement value is the speed measurement value of the main pump after power failure, and the second measurement value is the speed measurement value of the main pump at the instant of power failure.

[0092] If used t =0 indicates the state at the instant of power failure, then it can be used t>0 This indicates the state after the power outage described above, in this embodiment... t It can indicate the moment of power outage.

[0093] In step 120, after acquiring the first measurement sequence and the second measurement, the electronic device can further determine the initial decrease curve of the coolant flow rate in the primary loop.

[0094] The aforementioned initial decline curve can be used to represent the change curve of coolant flow rate in the primary circuit over a period of time when the main pump is powered off. For example, the initial decline curve may include the change curve of coolant flow rate in the primary circuit within 20 seconds after the main pump is powered off. The horizontal axis of the initial decline curve can represent time, such as from 1 second to 20 seconds, and the vertical axis of the initial decline curve can represent the proportion of coolant flow rate.

[0095] In some embodiments, if the first measurement sequence includes 20 measurements of coolant flow rate in the primary circuit of the main pump within 20 seconds after power failure, and the second measurement includes measurements of coolant flow rate in the primary circuit of the main pump at the instant of power failure, then the 20 measurements of coolant flow rate in the primary circuit within 20 seconds after power failure can be divided sequentially by the measured coolant flow rate in the primary circuit at the instant of power failure to obtain the decreasing curve of coolant flow rate of the main pump within 20 seconds after power failure, which is the aforementioned initial decreasing curve.

[0096] Taking one loop in a primary circuit as an example, the first measurement sequence includes 20 coolant flow rate measurements of the main pump within 20 seconds after a power outage. q i (1), q i (2),…, q i (20) ], where i represents the loop number of the main pump. The second measurement is the coolant flow rate in the primary loop of the main pump at the moment of power failure. q i (0) ,i This also indicates the loop number where the main pump is located. Accordingly, based on... q i (1) / q i (0) , ..., q i (20) / q i (0) Twenty calculated values ​​can be determined, and based on these 20 calculated values, the decrease curve of the coolant flow rate in the i-loop corresponding to the main pump within 20 seconds after power failure can be determined.

[0097] In some embodiments, if the first measurement sequence includes the rotational speed measurements of 20 main pumps within 20 seconds after power failure, and the second measurement is the rotational speed measurement of the main pump at the instant of power failure, then the rotational speed measurements of the 20 main pumps within 20 seconds after power failure can be sequentially divided by the rotational speed measurement of the main pump at the instant of power failure to obtain the cooling flow rate decline curve of the main pump within 20 seconds after power failure, which is the aforementioned initial decline curve.

[0098] Referring to the above example, if both the first and second measurement values ​​are speed measurement values, similarly, the 20 speed measurement values ​​[RPM] in the power-off state... i (1), RPM i (2),…, RPM i (20)] Speed ​​measurement value RPM at the moment of power failure i (0). Accordingly, according to RPM i (1) / RPM i (0), ..., RPM i (20) / RPM i (0) can determine 20 calculated values. Based on these 20 calculated values, the decrease curve of the coolant flow rate of the i-loop corresponding to the main pump within 20 seconds after power failure can be determined.

[0099] The coolant flow rate decrease curve of the i-circuit in the above loop This can be represented as follows, where t represents time:

[0100] (1).

[0101] In some embodiments, after determining the coolant flow rate decrease curves for each loop in a loop, the electronic device can determine the initial decrease curve of the coolant flow rate in the loop based on the coolant flow rate decrease curves for all loops in the loop. For example, if a loop includes three loops, the corresponding coolant flow rate decrease curves can be represented as follows: and ,according to 、 and The initial decrease curve of coolant flow rate in the primary loop can be determined. .

[0102] In step 130, after determining the initial drop curve of the coolant in the primary loop according to the above embodiment, the electronic device can further combine the steady-state flow rate of the coolant in each coolant loop in the primary loop of the nuclear reactor operating at different power levels to determine the target drop curve.

[0103] The aforementioned coolant steady-state flow rate represents the coolant flow rate in each loop of the primary loop system under stable operating conditions. The coolant steady-state flow rate is a crucial parameter for nuclear reactor operation; by monitoring the coolant steady-state flow rate in real time, any abnormalities during nuclear reactor operation can be detected promptly.

[0104] For example, the steady-state flow rate of the coolant is available It means that among them i Indicates the loop number, j Indicates power platform, different sizes j Corresponding to different power levels.

[0105] Electronic devices based on the initial descent curve include 、 and The absolute value of the steady-state flow rate of coolant in each coolant loop (collectively referred to as loop for ease of description) and each coolant loop. (like and ), determine the target descent curve.

[0106] In some embodiments, the electronic device can display the coolant flow rate decrease curve of loop 1 in a primary loop. Each value in the multiplier The coolant flow rate decrease curve is updated to reflect the coolant flow rate decrease curve of all loops. Once the coolant flow rate decrease curve of all loops has been updated, the target decrease curve can be determined based on the updated coolant flow rate decrease curve of all loops.

[0107] The coolant flow rate decrease curve of loop 1 above Each value in the multiplier The absolute value of the coolant flow rate at each moment in the coolant flow rate decline curve of loop 1 can be obtained. Using the absolute value of the coolant flow rate can improve the accuracy and reliability of the determined target decline curve, thereby improving the accuracy and reliability of the coasting performance test of the main pump.

[0108] In step 140, the electronic device can compare the target descent curve obtained in the above embodiment with the first preset coasting flow curve and the second preset coasting flow curve, thereby determining the performance test results of the main pump.

[0109] The first preset coasting flow curve and the second preset coasting curve correspond to the above-mentioned fast attenuation criterion and slow attenuation criterion. That is, the first preset coasting flow curve can be regarded as the above-mentioned fast attenuation criterion, and the second preset coasting curve can be regarded as the above-mentioned slow attenuation criterion.

[0110] The aforementioned target decline curve can be regarded as the decline curve of coolant flow in the primary circuit when the main pump is actually powered off.

[0111] Specifically, the electronic equipment can determine whether the DNBR of the reactor system exceeds the limit after the main pump is powered off, based on the first target descent curve and the first preset coasting flow curve.

[0112] The electronic equipment can determine whether overpressure will occur in the primary and secondary circuits after the main pump is powered off, based on the second target descent curve and the second preset coasting curve.

[0113] The electronic device can determine that the main pump's coasting performance is qualified if the first target decline curve is higher than the first preset coasting flow curve and the second target decline curve is lower than the second preset coasting flow curve; otherwise, it can determine that the main pump's coasting performance is unqualified.

[0114] In one possible implementation, after determining the initial decrease curve of the coolant flow rate in the primary loop based on the first measurement sequence and the second measurement, the method further includes:

[0115] Obtain the response time of detectors in a nuclear reactor;

[0116] The initial descent curve is updated based on the detector response time to obtain the updated initial descent curve;

[0117] Based on the initial descent curve and the steady-state coolant flow rates in each coolant loop of the first loop during reactor operation at different power levels, the target descent curve is determined, including:

[0118] The target descent curve is determined based on the updated initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels.

[0119] This application embodiment takes into account the lag in detector response time and updates the initial descent curve based on the detector response time. Using the updated initial descent curve can further improve the accuracy and reliability of the determined target descent curve.

[0120] For example, the updated initial descent curve It can be represented as follows:

[0121] (2);

[0122] in, , This indicates the detector's response time.

[0123] Accordingly, in the case of 3 loops, the updated initial descent curve Including the following sub-decline curves corresponding to the 3rd ring road 、 and .

[0124] In one possible implementation, the initial descent curve includes sub-descent curves corresponding to each coolant loop in a primary loop;

[0125] Based on the initial descent curve and the steady-state coolant flow rates in each coolant loop of the first loop during reactor operation at different power levels, the target descent curve is determined, including:

[0126] Based on the heat balance method, determine the absolute value of the steady-state flow rate and the value of the flow rate uncertainty of each coolant loop;

[0127] The target descent curve is determined based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor.

[0128] This application embodiment can further improve the reliability of coasting performance testing of the main pump by determining the flow uncertainty value corresponding to the steady-state flow of each loop and incorporating the flow uncertainty value into the determination process of the target descent curve.

[0129] The initial descent curves described above include sub-descent curves corresponding to each coolant loop (i.e., each loop) in the primary loop. Refer to the description in the foregoing embodiments. For example, the primary loop includes the three loops exemplified in the above embodiments, and the sub-descent curves corresponding to the three loops are as follows: 、 and .

[0130] The above-mentioned steady-state flow rate of the coolant can be found in the description of the foregoing embodiments, and will not be repeated here.

[0131] The aforementioned flow uncertainty refers to the non-negligible range of error caused by factors such as measurement error and system complexity when calculating the steady-state flow rate of the coolant. In some embodiments, the electronic equipment may determine this flow uncertainty based on measurement parameters of the nuclear reactor.

[0132] The above-mentioned heat balance method is based on the law of conservation of energy (the heat released by the reactor core plus the heat generated by the main pump equals the heat carried away by the secondary loop). According to the heat balance method, the absolute value of the steady-state flow rate of the coolant in each coolant loop and the value of the flow rate uncertainty can be found in relevant technologies, which will not be repeated here.

[0133] In some embodiments, the electronic device may determine the flow uncertainty value of the main pump of each loop when it coasts, based on the updated sub-decline curves of each loop and the coolant steady-state flow rate and its flow uncertainty value of each loop.

[0134] With the updated i Sub-descent curve of the loop Example, j Flow uncertainty of power platform It can be represented as follows:

[0135] (3);

[0136] in, express i Ring Road j The flow uncertainty value of the power platform (which may actually refer to the steady-state flow measurement uncertainty value).

[0137] Based on the above formula, the uncertainty value of the total flow rate of all loops in the primary loop when the main pump is coasting can be determined.

[0138] In some embodiments, the target descent curve is determined based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor, including:

[0139] The target descent curve is determined based on the updated sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow uncertainty value, and the design flow rate of the nuclear reactor.

[0140] For example, the target descent curve It can be represented as follows:

[0141] (4);

[0142] in, This indicates the design flow rate.

[0143] In one possible implementation, the target descent curve includes a first target descent curve, and the design flow rate includes the thermal design flow rate.

[0144] Based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor, the target descent curve is determined, including:

[0145] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0146] Based on all intermediate descent curves, flow uncertainty values, and thermal design flow rates, the first target descent curve is determined.

[0147] As mentioned above, by updating formula (4) in the above embodiments, the first target descent curve can be obtained. It is expressed as follows:

[0148] (5);

[0149] in, This represents the thermal design flow rate mentioned above.

[0150] In one possible implementation, the target descent curve includes a second target descent curve, and the design flow rate includes the mechanical design flow rate;

[0151] Based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor, the target descent curve is determined, including:

[0152] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0153] The second target descent curve is determined based on all intermediate descent curves, flow uncertainty values, and mechanical design flow rates.

[0154] As mentioned above, by updating formula (4) in the above embodiments, the second target descent curve can be obtained. It is expressed as follows:

[0155] (6);

[0156] in, This indicates the design flow rate of the aforementioned machinery.

[0157] In one possible implementation, before determining the performance test results of the main pump based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, the method further includes:

[0158] Obtain the range of the first assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0159] Based on the uncertainty parameter range of the first assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events in the nuclear reactor under the design reference condition, the occurrence frequency of each transient event, and the deviation nucleus boiling risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0160] Based on the frequency of occurrence of each transient event and the deviation from the boiling risk value corresponding to each transient event, the first target transient event is determined from multiple transient events, and the operating condition corresponding to the first target transient event is the first target operating condition;

[0161] When the deviation from nucleation boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold, the range of the first initial uncertainty parameter is determined.

[0162] Based on the first initial uncertainty parameter range, the first preset working condition is simulated to obtain the first target uncertainty parameter range;

[0163] Based on the uncertainty parameter range of the first objective, the first objective operating condition is simulated to obtain the first preset coasting flow curve.

[0164] In this embodiment of the application, when the moment of inertia of the main pump and its first uncertainty parameter range simultaneously meet the first target operating condition and the first preset operating condition, the coasting flow curve simulated under the first target operating condition can be used as the first preset coasting flow curve. The first preset coasting flow curve can be used as the above-mentioned rapid decay criterion. By adopting the first preset coasting flow curve in this embodiment of the application, the accuracy of judging whether the main pump meets the DNB requirements after power failure can be improved, thereby improving the accuracy and comprehensiveness of the coasting performance test of the main pump.

[0165] The aforementioned moment of inertia refers to the theoretical moment of inertia of the main pump's idler flywheel during the design phase, and can be determined using the value provided by the idler flywheel manufacturer. Moment of inertia determines the rate of flow rate decay of the main pump after power failure; generally, the larger the moment of inertia, the longer the idler time and the slower the flow rate decay.

[0166] In some embodiments, the electronic device can determine the aforementioned moment of inertia by the geometry and material density of the idler flywheel.

[0167] The aforementioned range of the first uncertainty parameter can be used to represent the allowable fluctuation range of the moment of inertia.

[0168] For details on the probabilistic safety analysis and thermal-hydraulic simulation described above, please refer to the relevant technical introductions, which will not be repeated here.

[0169] The aforementioned transient events can represent events that, under the design baseline operating conditions of a nuclear power plant, may lead to the complete or partial shutdown of the main pumps. For example, a short-term loss of external power.

[0170] The above frequency of occurrence can represent the probability density of transient events occurring within the operating cycle of a nuclear power plant, and its unit is the number of occurrences per reactor per year.

[0171] The aforementioned deviation from the nucleus boiling risk value can be represented by DNBR in the previous embodiments, and will not be repeated here.

[0172] If the deviation from the nucleus boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold (or greater than the first preset safety threshold with a certain margin), it indicates that the main pump's rotational inertia and its corresponding first uncertainty parameter range can meet the DNB safety requirements. If not, the first uncertainty parameter range can be adjusted, and based on the adjusted first uncertainty parameter range, it can be further determined whether the DNB safety requirements are met.

[0173] If the DNB safety requirements are met and a certain margin is allowed (i.e., the deviation from the nucleation boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold), it is possible to continue to verify whether the range of the first uncertainty parameter meets the DNB safety requirements of the first preset operating condition. If it does not meet the requirements, the corresponding range of the first uncertainty parameter can be adjusted, and based on the adjusted range of the first uncertainty parameter, it is possible to continue to determine whether the DNB safety requirements are met.

[0174] Based on the first preset operating condition, if the DNB safety requirements are still met and a certain margin is left, the main pump can be simulated for coasting based on the first uncertainty parameter range and the first target operating condition to obtain the first preset coasting flow curve of the first loop.

[0175] The aforementioned first preset coasting flow curve can be input into electronic equipment as a basis for judging the test results.

[0176] In this embodiment of the application, the main pump coasting is simulated based on the first uncertainty parameter range and the first target operating condition. In fact, the main pump coasting is simulated based on the lower limit of the first uncertainty parameter range and the first target operating condition.

[0177] In one possible implementation, before determining the performance test results of the main pump based on the target descent curve, the first preset coasting flow rate curve, and the second preset coasting flow rate curve, the method further includes:

[0178] Obtain the range of the second assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0179] Based on the uncertainty parameter range of the second assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events corresponding to the load conditions in the nuclear reactor, the occurrence frequency of each transient event, and the overpressure risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0180] Based on the frequency of occurrence of each transient event and the overpressure risk value corresponding to each transient event, a second target transient event is determined from multiple transient events, and the operating condition corresponding to the second target transient event is the second target operating condition;

[0181] If the overpressure risk value corresponding to the second target working condition is less than the second preset safety threshold, determine the range of the second initial uncertainty parameter.

[0182] Based on the second initial uncertainty parameter range, the second preset working condition is simulated to obtain the second target uncertainty parameter range;

[0183] Based on the uncertainty parameter range of the second objective, the second objective operating condition is simulated to obtain the second preset coasting flow curve.

[0184] In this embodiment of the application, when the rotational inertia of the main pump and the range of its second uncertainty parameter simultaneously meet the second target operating condition and the second preset operating condition, the coasting flow curve simulated under the second target operating condition can be used as the second preset coasting flow curve. The second preset coasting flow curve can be used as the above-mentioned slow decay criterion. By adopting the second preset coasting flow curve in this embodiment of the application, the accuracy of judging whether the main pump will cause overpressure in the primary and secondary circuit systems after power failure can be improved, thereby improving the accuracy and comprehensiveness of the coasting performance test of the main pump.

[0185] In this embodiment of the application, the inertia of the main pump is simulated based on the second uncertainty parameter range and the second target operating condition. In fact, the inertia of the main pump is simulated based on the upper limit of the second uncertainty parameter range and the second target operating condition.

[0186] The range of the second uncertainty parameter mentioned above can be referred to the description of the range of the first uncertainty parameter in the foregoing embodiments.

[0187] The above probabilistic safety analysis, thermal-hydraulic simulation, transient events, and occurrence frequency can be referred to the descriptions in the foregoing embodiments.

[0188] The process of determining the second preset idler flow curve in this embodiment can be referred to the description of determining the first preset idler flow curve in the previous embodiment, and will not be repeated here.

[0189] The aforementioned second preset operating condition includes the overpressure consequences analysis of the main pump's complete or partial shutdown under the design baseline operating condition and the design extended operating condition.

[0190] Please see Figure 2 , Figure 2 The flowchart illustrates the determination of a preset coasting flow rate curve in a performance testing method for a nuclear reactor coolant pump provided in this application embodiment.

[0191] by Figure 2 The example shown on the left side of the diagram illustrates the determination of the rapid attenuation criterion, which establishes the uncertainty assumption regarding the main pump's rotational inertia in the safety analysis (corresponding to the first uncertainty parameter range for the main pump's rotational inertia mentioned above). The constant-volume operating condition corresponds to the first target operating condition mentioned above. The design extended operating condition, including the main pump complete or partial shutdown condition and the design baseline operating condition after superimposing the loss of external power supply (LOOP) assumption (i.e., assuming the loss of external power supply simultaneously with the accident), corresponds to the first preset operating condition mentioned above.

[0192] In one possible implementation, the performance test results of the main pump are determined based on the target descent curve, a first preset numerical curve, and a second preset numerical curve, including:

[0193] If, at the same time point, the value of the first target decline curve is greater than the value corresponding to the first preset value curve, and the value of the second target decline curve is less than the value corresponding to the second preset value curve, then the performance test result is deemed qualified.

[0194] Please see Figure 3 and Figure 4 ,in, Figure 3 This is a comparative schematic diagram involving a performance testing method for a nuclear reactor coolant pump provided in an embodiment of this application. Figure 4 This is another comparative schematic diagram related to a performance testing method for a nuclear reactor coolant pump provided in an embodiment of this application. Figure 3 and Figure 4 The vertical axis represents the percentage of coolant flow, and the horizontal axis represents time.

[0195] exist Figure 3 In the diagram, the dashed line represents the second preset coasting flow curve, and the straight line represents the second target descent curve.

[0196] exist Figure 4 In the diagram, the dashed line represents the first preset coasting flow curve, and the straight line represents the first target descent curve.

[0197] Combination Figure 3 and Figure 4 It can be observed that, at the same time point, the coasting flow rate of the first target descent curve is greater than the coasting flow rate corresponding to the first preset coasting flow rate curve, and the coasting flow rate of the second target descent curve is less than the coasting flow rate corresponding to the second preset coasting flow rate curve. Therefore, it can be determined that the coasting performance of the main pump is qualified.

[0198] Corresponding to the above method embodiments, this application also provides a performance testing system for a nuclear reactor coolant pump. Please refer to [link to relevant documentation]. Figure 5 , Figure 5 A functional module diagram of a performance testing system for a nuclear reactor coolant pump provided in this application embodiment is shown, wherein the nuclear reactor coolant pump performance testing system 500 includes:

[0199] The acquisition module 510 is used to acquire a first measurement value sequence of the main pump in the nuclear reactor after power failure, and a second measurement value of the main pump at the moment of power failure. The first measurement value sequence includes multiple first measurement values, and the main pump is the coolant pump in the nuclear reactor.

[0200] The first determining module 520 is used to determine the initial decreasing curve of the coolant flow rate in a primary loop based on the first measurement value sequence and the second measurement value.

[0201] The second determining module 530 is used to determine the target decreasing curve based on the initial decreasing curve and the steady-state flow rate of coolant in each coolant loop of the primary loop of the nuclear reactor under different power operation conditions.

[0202] The third determining module 540 is used to determine the performance test results of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve. The first preset coasting flow curve and the second preset coasting flow curve are obtained based on the preset safety analysis results. The first preset coasting flow curve and the second preset coasting flow curve are used to indicate whether the performance test results meet the safety analysis requirements.

[0203] The performance testing system for nuclear reactor coolant pumps provided in this application embodiment can achieve, for example... Figure 1 The various processes implemented in the Chinese method embodiments can achieve similar or the same technical effects, and will not be described again here to avoid repetition.

[0204] In one possible implementation, the first measurement value is the measurement value of the coolant flow rate in the first circuit after power failure, and the second measurement value is the measurement value of the coolant flow rate in the first circuit at the instant of power failure.

[0205] Alternatively, the first measurement value is the speed measurement value of the main pump after power failure, and the second measurement value is the speed measurement value of the main pump at the instant of power failure.

[0206] In one possible implementation, the initial descent curve includes sub-descent curves corresponding to each coolant loop in a primary loop;

[0207] The second determining module 530 is also used for:

[0208] Based on the heat balance method, determine the absolute value of the steady-state flow rate and the value of the flow rate uncertainty of each coolant loop;

[0209] The target descent curve is determined based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor.

[0210] In one possible implementation, the target descent curve includes a first target descent curve, and the design flow rate includes the thermal design flow rate.

[0211] The second determining module 530 includes a first determining submodule, which is used for:

[0212] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0213] Based on all intermediate descent curves, flow uncertainty values, and the thermal design flow rate, the first target descent curve is determined.

[0214] In one possible implementation, the target descent curve includes a second target descent curve, and the design flow rate includes the mechanical design flow rate;

[0215] The second determining module 530 includes a second determining submodule, which is used for:

[0216] For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, resulting in multiple intermediate decline curves corresponding to the entire coolant loop. The coolant loop and the intermediate decline curve correspond one-to-one.

[0217] The second target descent curve is determined based on all intermediate descent curves, the flow uncertainty value, and the mechanical design flow rate.

[0218] In one possible implementation, the nuclear reactor coolant pump performance testing system 500 further includes an update module for:

[0219] Obtain the response time of detectors in a nuclear reactor;

[0220] The initial descent curve is updated based on the detector response time to obtain the updated initial descent curve;

[0221] The second determining module 530 is also specifically used for:

[0222] The target descent curve is determined based on the updated initial descent curve and the steady-state coolant flow rate of each coolant loop in the first loop of the nuclear reactor operating at different power levels.

[0223] In one possible implementation, the nuclear reactor coolant pump performance testing system 500 further includes a first analysis module, which is used for:

[0224] Obtain the range of the first assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0225] Based on the uncertainty parameter range of the first assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events in the nuclear reactor under the design reference condition, the occurrence frequency of each transient event, and the deviation nucleus boiling risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0226] Based on the frequency of occurrence of each transient event and the deviation from the boiling risk value corresponding to each transient event, the first target transient event is determined from multiple transient events, and the operating condition corresponding to the first target transient event is the first target operating condition;

[0227] When the deviation from nucleation boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold, the range of the first initial uncertainty parameter is determined.

[0228] Based on the first initial uncertainty parameter range, the first preset working condition is simulated to obtain the first target uncertainty parameter range;

[0229] Based on the uncertainty parameter range of the first objective, the first objective operating condition is simulated to obtain the first preset coasting flow curve.

[0230] In one possible implementation, the nuclear reactor coolant pump performance testing system 500 further includes a second analysis module, which is used for:

[0231] Obtain the range of the second assumption uncertainty parameter corresponding to the moment of inertia of the main pump;

[0232] Based on the uncertainty parameter range of the second assumption, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events corresponding to the load conditions in the nuclear reactor, the occurrence frequency of each transient event, and the overpressure risk value corresponding to each transient event. The shutdown condition is the operating condition of the main pump after power failure.

[0233] Based on the frequency of occurrence of each transient event and the overpressure risk value corresponding to each transient event, a second target transient event is determined from multiple transient events, and the operating condition corresponding to the second target transient event is the second target operating condition;

[0234] If the overpressure risk value corresponding to the second target working condition is less than the second preset safety threshold, determine the range of the second initial uncertainty parameter.

[0235] Based on the second initial uncertainty parameter range, the second preset working condition is simulated to obtain the second target uncertainty parameter range;

[0236] Based on the uncertainty parameter range of the second objective, the second objective operating condition is simulated to obtain the second preset coasting flow curve.

[0237] In one possible implementation, the third determining module 540 is further specifically used for:

[0238] If, at the same time point, the value of the first target decline curve is greater than the value corresponding to the first preset value curve, and the value of the second target decline curve is less than the value corresponding to the second preset value curve, then the performance test result is deemed qualified.

[0239] This application also provides an electronic device. Please refer to [link to previous application]. Figure 6 , Figure 6 This is a diagram illustrating the internal structure of an electronic device according to an embodiment of this application. The electronic device includes a processor, a memory, and a network interface connected via a system bus. The memory includes a non-volatile storage medium and internal memory. The non-volatile storage medium stores an operating system and may also store a computer program. When executed by the processor, this computer program enables the processor to implement the performance testing method for the nuclear reactor coolant pump applied to the electronic device in the above embodiment. The internal memory may also store a computer program, which, when executed by the processor, enables the processor to execute the performance testing method for the nuclear reactor coolant pump. Those skilled in the art will understand that... Figure 6 The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the electronic device to which the present application is applied. The specific electronic device may include more or fewer components than shown in the figure, or combine certain components, or have different component arrangements.

[0240] This application also discloses a computer-readable storage medium storing a computer program. When the computer program is executed by a processor, it implements the performance testing method for a nuclear reactor coolant pump as described in the method embodiment.

[0241] This application provides a computer program product stored in a storage medium. The program product is executed by at least one processor to implement various processes of the embodiment of the performance testing method for nuclear reactor coolant pump described above, and can achieve similar or the same technical effects. To avoid repetition, it will not be described again here.

[0242] Those skilled in the art will understand that all or part of the processes in the methods of the above embodiments can be implemented by a computer program instructing related hardware. This program can be stored in a non-volatile computer-readable storage medium, and when executed, it can include the processes of the embodiments of the above methods. Any references to memory, storage, databases, or other media used in the embodiments provided in this application can include non-volatile and / or volatile memory. Non-volatile memory can include read-only memory (ROM), programmable ROM (PROM), electrically programmable ROM (EPROM), electrically erasable programmable ROM (EEPROM), or flash memory. Volatile memory can include random access memory (RAM) or external cache memory. By way of illustration and not limitation, RAM is available in various forms, such as static RAM (SRAM), dynamic RAM (DRAM), synchronous DRAM (SDRAM), dual data rate SDRAM (DDRSDRAM), enhanced SDRAM (ESDRAM), synchronous link DRAM (SLDRAM), RAMbus direct RAM (RDRAM), direct memory bus dynamic RAM (DRDRAM), and RAMbus dynamic RAM (RDRAM), etc.

[0243] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

Claims

1. A performance testing method for a nuclear reactor coolant pump, characterized in that, The method includes: The first measurement value sequence of the main pump in the nuclear reactor after power failure and the second measurement value of the main pump at the moment of power failure are obtained. The first measurement value sequence includes multiple first measurement values. The main pump is the coolant pump in the nuclear reactor. Based on the first measurement sequence and the second measurement, determine the initial decrease curve of the coolant flow rate in the primary loop; Based on the initial descent curve and the steady-state coolant flow rate of each coolant loop in the primary loop of the nuclear reactor under different power operating conditions, the target descent curve is determined. The performance test results of the main pump are determined based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve. The first preset coasting flow curve and the second preset coasting flow curve are obtained based on the preset safety analysis results. The first preset coasting flow curve and the second preset coasting flow curve are used to indicate whether the performance test results meet the safety analysis requirements.

2. The method according to claim 1, characterized in that, The first measurement value is the measurement value of the coolant flow rate in the first circuit under the state after power failure, and the second measurement value is the measurement value of the coolant flow rate in the first circuit under the state at the instant of power failure; Alternatively, the first measurement value is the speed measurement value of the main pump in the state after power failure, and the second measurement value is the speed measurement value of the main pump in the state at the instant of power failure.

3. The method according to claim 1, characterized in that, The initial descent curve includes sub-descent curves corresponding to each coolant loop in the primary loop; The determination of the target decline curve based on the initial decline curve and the steady-state coolant flow rate of each coolant loop in the primary loop of the nuclear reactor under different power operating conditions includes: Based on the heat balance method, determine the absolute value of the steady-state flow rate and the value of the flow rate uncertainty of each coolant loop; The target descent curve is determined based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor.

4. The method according to claim 3, characterized in that, After determining the initial decrease curve of coolant flow rate in a primary loop based on the first measurement value sequence and the second measurement value, the method further includes: Obtain the detector response time in the nuclear reactor; The initial descent curve is updated based on the detector response time to obtain the updated initial descent curve; The determination of the target decline curve based on the initial decline curve and the steady-state coolant flow rate of each coolant loop in the primary loop of the nuclear reactor under different power operating conditions includes: The target decline curve is determined based on the updated initial decline curve and the steady-state coolant flow rate of each coolant loop in the primary loop of the nuclear reactor under different power operating conditions.

5. The method according to claim 3, characterized in that, The target descent curve includes a first target descent curve, and the design flow rate includes the thermal design flow rate; The step of determining the target descent curve based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor includes: For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, so as to obtain multiple intermediate decline curves corresponding to the entire coolant loop, and the coolant loop and the intermediate decline curves correspond one-to-one. The first target descent curve is determined based on all the intermediate descent curves, the flow uncertainty value, and the thermal design flow rate.

6. The method according to claim 5, characterized in that, The target descent curve includes a second target descent curve, and the design flow rate includes the mechanical design flow rate; The step of determining the target descent curve based on the sub-descent curves corresponding to each coolant loop, the steady-state flow rate of the coolant, the flow rate uncertainty value, and the design flow rate of the nuclear reactor includes: For each coolant loop in the entire coolant loop, the sub-decline curve corresponding to the coolant loop is updated according to the coolant steady-state flow rate of the coolant loop, so as to obtain multiple intermediate decline curves corresponding to the entire coolant loop, and the coolant loop and the intermediate decline curves correspond one-to-one. The second target descent curve is determined based on all the intermediate descent curves, the flow uncertainty value, and the mechanical design flow rate.

7. The method according to claim 6, characterized in that, The step of determining the performance test results of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve includes: If, at the same time point, the value of the first target decline curve is greater than the value corresponding to the first preset idle flow curve, and the value of the second target decline curve is less than the value corresponding to the second preset idle flow curve, then the performance test result is deemed qualified.

8. The method according to claim 1, characterized in that, Before determining the performance test result of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve, the method further includes: Obtain the range of the first assumption uncertainty parameter corresponding to the moment of inertia of the main pump; Based on the first assumed uncertainty parameter range, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events in the nuclear reactor under the design reference condition, the occurrence frequency of each transient event, and the deviation nucleus boiling risk value corresponding to each transient event. The shutdown condition is the condition corresponding to the main pump after the power failure. Based on the occurrence frequency of each transient event and the deviation from the boiling risk value corresponding to each transient event, a first target transient event is determined from multiple transient events, and the operating condition corresponding to the first target transient event is the first target operating condition; If the deviation from nucleation boiling risk value corresponding to the first target operating condition is greater than the first preset safety threshold, the range of the first initial uncertainty parameter is determined. Based on the first initial uncertainty parameter range, a working condition simulation is performed on the first preset working condition to obtain the first target uncertainty parameter range; Based on the first target uncertainty parameter range, the first target operating condition is simulated to obtain the first preset coasting flow curve.

9. The method according to claim 1, characterized in that, Before determining the performance test result of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve, the method further includes: Obtain the range of the second assumption uncertainty parameter corresponding to the moment of inertia of the main pump; Based on the second assumption of uncertainty parameter range, probabilistic safety analysis and thermal-hydraulic simulation are performed on the shutdown condition of the main pump to determine multiple transient events corresponding to the load conditions in the nuclear reactor, the occurrence frequency of each transient event, and the overpressure risk value corresponding to each transient event. The shutdown condition is the condition corresponding to the main pump after the power failure. Based on the occurrence frequency of each transient event and the overpressure risk value corresponding to each transient event, a second target transient event is determined from multiple transient events, and the operating condition corresponding to the second target transient event is the second target operating condition; If the overpressure risk value corresponding to the second target working condition is less than the second preset safety threshold, determine the range of the second initial uncertainty parameter. Based on the second initial uncertainty parameter range, the second preset working condition is simulated to obtain the second target uncertainty parameter range; Based on the uncertainty parameter range of the second target, the second target operating condition is simulated to obtain the second preset coasting flow curve.

10. A performance testing system for a nuclear reactor coolant pump, characterized in that, The system includes: The acquisition module is used to acquire a first measurement value sequence of the main pump in the nuclear reactor after power failure, and a second measurement value of the main pump at the moment of power failure. The first measurement value sequence includes multiple first measurement values, and the main pump is the coolant pump in the nuclear reactor. The first determining module is used to determine the initial decreasing curve of the coolant flow rate in a primary loop based on the first measurement value sequence and the second measurement value. The second determining module is used to determine the target decreasing curve based on the initial decreasing curve and the steady-state flow rate of coolant in each coolant loop of the primary loop under different power operation of the nuclear reactor; The third determining module is used to determine the performance test result of the main pump based on the target descent curve, the first preset coasting flow curve, and the second preset coasting flow curve. The first preset coasting flow curve and the second preset coasting flow curve are obtained based on preset safety analysis results. The first preset coasting flow curve and the second preset coasting flow curve are used to indicate whether the performance test result meets the safety analysis requirements.

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