Method for measuring heat dissipation loss power of primary loop of nuclear power station

Abstract

The invention discloses a method for measuring heat dissipation loss power of a primary loop of a nuclear power station, which comprises the following steps of: respectively acquiring thermal power input to the primary loop by an RCP main pump, an RCV pump and an electric heater of a primary loop voltage stabilizer during a test period by adjusting the running state of a unit to meet a preset test condition; and respectively acquiring the heat power output from the primary loop by the main pump heat shield cooling water, the RCV discharge heat exchanger, the primary loop leakage and the steam generator during the test period, and calculating the heat dissipation loss power of the primary loop by utilizing the law of conservation of energy according to the heat power input to the primary loop and the heat power output from the primary loop. According to the method, various influence factors of heat input and heat output of the primary loop are determined, the specific unit state meeting the measurement requirement is configured, accurate measurement of the heat dissipation loss power of the primary loop is achieved, the measurement process is relatively simple and convenient, and the technical vacancy that the heat dissipation loss power of the primary loop of the nuclear power station is difficult to measure in the prior art is made up.

Description

Technical Field

[0001] The invention belongs to the field of nuclear power performance testing, and in particular relates to a method for measuring the heat dissipation loss power of a primary circuit of a nuclear power plant. Background Art

[0002] In the primary loop of a nuclear power plant reactor, the reactor core, main pump and pressurizer electric heater provide heat, the steam generator (SG), chemical and volume control system discharge heat exchanger, main pump heat shield cooling water, primary loop leakage, primary loop heat dissipation take away heat, and the overall energy balance between providing heat and taking away heat. If a new reactor type is used in a new nuclear power plant, the primary loop heat dissipation power loss must be measured to evaluate whether the actual primary loop heat dissipation power loss is consistent with the initial design, and to determine the final overall thermal power design value of the nuclear island. However, in the prior art, the actual primary loop heat dissipation power loss cannot be directly measured by instruments and meters. Therefore, there are great technical difficulties in accurately measuring the primary loop heat dissipation power loss. Summary of the invention

[0003] The purpose of the present invention is to provide a method for measuring the heat dissipation loss power of a primary circuit of a nuclear power plant. The method measures the thermal power input to the primary circuit and the thermal power output from the primary circuit under preset test conditions, and calculates the heat dissipation loss power of the primary circuit based on the thermal power input and the thermal power output by using the law of conservation of energy, thereby solving the technical problem that the heat dissipation loss power of a primary circuit of a nuclear power plant is difficult to measure in the prior art.

[0004] In order to solve the above technical problems, the present invention is achieved through the following technical solutions:

[0005] The present invention provides a method for measuring the heat dissipation loss power of a primary circuit of a nuclear power plant, which comprises:

[0006] Adjust the unit operating status until the preset test conditions are met;

[0007] Manually control the opening of the ARE water supply regulating valve to replenish the liquid level of the steam generator to the preset high liquid level. When the average temperature of the primary circuit is stable, manually close the ARE water supply regulating valve and the isolation valve, and record the start time of test data collection;

[0008] During the test data collection, the GCT regulating valve opening is automatically controlled by setting the main steam pressure constant, and the primary circuit pressure, primary circuit average temperature and main steam pressure are maintained stable. When the steam generator liquid level drops to the preset low liquid level, the test data collection is stopped and the end time of the test data collection is recorded;

[0009] Obtain the heat power input to the primary circuit by the RCP main pump, RCV pump and the electric heater of the primary circuit regulator during the test;

[0010] The thermal power output from the main pump heat shield cooling water, RCV downflow heat exchanger, primary circuit leakage and steam generator from the primary circuit during the test is obtained respectively;

[0011] The heat dissipation loss power of the primary circuit is calculated by utilizing the law of conservation of energy according to the heat power input to the primary circuit and the heat power output from the primary circuit.

[0012] In one embodiment of the present invention, the preset test conditions include:

[0013] The nuclear reactor is in hot shutdown mode;

[0014] The primary circuit pressure, primary circuit average temperature and main steam pressure are within the preset range;

[0015] The main steam generated by the steam generator is discharged to the condenser through the GCT system;

[0016] The main pump shaft seal returns to the RCV system, and the RCV downflow to the TEP system coolant storage tank and degassing pipeline has been isolated;

[0017] The control channels of the primary circuit regulator pressure, primary circuit regulator liquid level and steam generator liquid level are in automatic mode, and the steam generator liquid level alarm signal and the action signal for triggering protection have been forcibly set;

[0018] The steam generator secondary sampling line has been isolated and the steam generator blowdown is closed;

[0019] The RCV control tank has been filled to the preset height and the REA system is in automatic replenishment mode;

[0020] The water supply regulating valve from the ARE system to the steam generator is placed in manual control mode.

[0021] In one embodiment of the present invention, the method for measuring the power loss of heat dissipation in the first circuit of a nuclear power plant further includes: stopping the test when the liquid level of the steam generator drops to a preset low liquid level, and resuming opening the water supply regulating valve and the isolation valve from the ARE system to the steam generator, and placing the water supply regulating valve and the isolation valve from the ARE system to the steam generator in automatic control mode.

[0022] In one embodiment of the present invention, the step of respectively obtaining the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test includes:

[0023] Acquire test data of the RCP main pump, RCV pump and the electric heater of the primary circuit regulator during the test respectively;

[0024] According to the test data, the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator is obtained.

[0025] In one embodiment of the present invention, the step of respectively acquiring test data of the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test includes:

[0026] Obtain the average motor power and motor efficiency of the three RCP main pumps during the test;

[0027] Obtain the average motor power and motor efficiency of the RCV pump during the test;

[0028] Obtain the opening setting value of each electric heater of the primary circuit voltage stabilizer and the average actual power supply voltage during the test.

[0029] In one embodiment of the present invention, the step of obtaining the thermal power input to the primary circuit by the electric heater of the RCP main pump, the RCV pump and the primary circuit regulator according to the test data comprises:

[0030] The average motor power of the three RCP main pumps is multiplied by the motor efficiency and then summed to obtain the thermal power input by the RCP main pump to the primary circuit;

[0031] Multiplying the average motor power of the RCV pump by the motor efficiency to obtain the thermal power input by the RCV pump to the primary circuit;

[0032] According to the opening setting value of each electric heater of the primary circuit regulator and the average actual power supply voltage, the power of each electric heater is calculated respectively, and the power of each electric heater is summed to obtain the thermal power input by the electric heater of the regulator to the primary circuit.

[0033] In one embodiment of the present invention, the heat power outputted from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test is obtained respectively, including:

[0034] Obtain the test data of the main pump heat shield cooling water, RCV downflow heat exchanger, primary circuit leakage and steam generator during the test;

[0035] According to the test data, the thermal power output from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator is obtained.

[0036] In one embodiment of the present invention, the test data of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test are respectively obtained, including:

[0037] Obtain the fluid inlet pressure, inlet and outlet temperatures and flow rate on the RRI side of the main pump heat shield during the test;

[0038] Obtain the fluid inlet pressure, inlet and outlet temperature, flow rate of the RCV side of the RCV downstream heat exchanger and the fluid inlet pressure, inlet and outlet temperature, flow rate of the RRI side during the test;

[0039] Obtain the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply, boric acid pressure, boric acid temperature, desalted water supply, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start and end time of test data collection respectively;

[0040] respectively obtaining the steam generator liquid level at the start time of test data collection and the steam generator liquid level and steam generator pressure at the end time of test data collection;

[0041] If there are multiple measurement points in the measurement data, the average value of the multiple measurement points at the same time is calculated.

[0042] In one embodiment of the present invention, the step of obtaining the thermal power output of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator from the primary circuit based on the test data includes:

[0043] According to the inlet pressure, inlet and outlet temperature and flow rate of the fluid on the RRI side of the main pump heat shield, the thermal power output of the main pump heat shield cooling water from the primary circuit is calculated;

[0044] Calculate the thermal power output of the RCV downstream heat exchanger from the primary circuit according to the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RCV side of the operating RCV downstream heat exchanger and the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RRI side;

[0045] According to the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply, boric acid pressure, boric acid temperature, desalted water supply, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start and end time of test data collection, the thermal power output from the primary circuit by the leakage of the primary circuit is calculated;

[0046] The thermal power output of the steam generator from the primary circuit is obtained by calculation according to the steam generator liquid level at the start time of the test data collection and the steam generator liquid level and the steam generator pressure at the end time of the test data collection.

[0047] In one embodiment of the present invention, the heat loss power of the primary circuit is calculated by using the law of conservation of energy according to the heat power input to the primary circuit and the heat power output from the primary circuit, including:

[0048] The sum of the thermal powers input to the primary circuit by the RCP main pump, RCV pump and the electric heater of the primary circuit regulator is subtracted from the sum of the thermal powers output from the primary circuit by the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator to obtain the heat dissipation loss power of the primary circuit.

[0049] As described above, the present invention provides a method for measuring the power loss of heat dissipation in a primary circuit of a nuclear power plant, which has the following beneficial effects: by adjusting the operating state of the unit until the preset test conditions are met, manually controlling the opening of the ARE water supply regulating valve to replenish the liquid level of the steam generator to a preset high liquid level, manually closing the ARE water supply regulating valve and the isolation valve when the average temperature of the primary circuit is stable, and recording the start time of the test data collection, automatically controlling the opening of the GCT regulating valve by setting the main steam pressure constant during the test data collection, and maintaining the primary circuit pressure, the primary circuit average temperature and the main steam pressure stable, stopping the test data collection when the steam generator liquid level drops to a preset low liquid level, and recording the end time of the test data collection, respectively obtaining the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test, respectively obtaining the thermal power output from the primary circuit by the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test, and calculating the power loss of heat dissipation in the primary circuit according to the thermal power input to the primary circuit and the thermal power output from the primary circuit by the law of conservation of energy. The method determines various influencing factors of heat input and heat output of a circuit, and configures a specific unit state that meets the test requirements to achieve accurate measurement of heat loss power of a circuit, and the measurement process is relatively simple, which makes up for the vacancy in the prior art that the heat loss power of a circuit of a nuclear power plant is difficult to measure. Of course, any product implementing the present invention does not necessarily need to achieve all the advantages described above at the same time. BRIEF DESCRIPTION OF THE DRAWINGS

[0050] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings required for describing the embodiments will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other accompanying drawings can be obtained based on these accompanying drawings without paying creative work.

[0051] Figure 1 A flowchart of a method for measuring the heat dissipation loss power of a nuclear power plant primary circuit provided by an exemplary embodiment of the present application.

[0052] Figure 2 A schematic diagram of a flow chart for obtaining thermal power input to a circuit is provided for an exemplary embodiment of the present application.

[0053] Figure 3 A schematic diagram of a flow chart for obtaining test data of an RCP main pump, an RCV pump and a pressurizer electric heater provided for an exemplary embodiment of the present application.

[0054] Figure 4 A schematic diagram of a flow chart for obtaining the thermal power input to a circuit by an RCP main pump, an RCV pump and a pressurizer heater is provided as an exemplary embodiment of the present application.

[0055] Figure 5 A schematic diagram of a flow chart for obtaining thermal power output from a circuit provided in accordance with an exemplary embodiment of the present application.

[0056] Figure 6 A schematic diagram of a flow chart for obtaining test data of main pump heat shield cooling water, RCV downstream heat exchanger, primary circuit leakage and steam generator provided for an exemplary embodiment of the present application.

[0057] Figure 7 A schematic diagram of a flow chart for obtaining the heat shield cooling water of a main pump, an RCV downstream heat exchanger, a primary circuit leakage, and the thermal power output from a primary circuit of a steam generator is provided as an exemplary embodiment of the present application. DETAILED DESCRIPTION

[0058] The following describes the embodiments of the present invention by specific examples, and those skilled in the art can easily understand other advantages and effects of the present invention from the contents disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed in various ways based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that the following embodiments and features in the embodiments can be combined with each other without conflict.

[0059] It should be noted that the illustrations provided in the following embodiments are only schematic illustrations of the basic concept of the present invention, and thus the drawings only show components related to the present invention rather than being drawn according to the number, shape and size of components in actual implementation. In actual implementation, the type, quantity and proportion of each component may be changed arbitrarily, and the component layout may also be more complicated.

[0060] In the following description, numerous details are discussed to provide a more thorough explanation of the embodiments of the present invention. However, it is obvious to those skilled in the art that the embodiments of the present invention can be implemented without these specific details. In other embodiments, well-known structures and devices are shown in the form of block diagrams rather than in detail to avoid making the embodiments of the present invention difficult to understand.

[0061] The primary circuit of a nuclear power plant refers to the reactor coolant system (RCP for short). Water is used as a coolant and circulates continuously in a closed circuit, transferring the heat absorbed from the nuclear reactor core to the steam generator. Specifically, the reactor core generates huge heat energy due to the fission of nuclear fuel. The water pumped into the core by the main pump is heated into high-temperature and high-pressure water. The high-temperature and high-pressure water flows through the heat transfer U-tube in the steam generator, and transfers the heat energy to the secondary circuit cooling water outside the heat transfer U-tube through the tube wall, causing it to evaporate into steam, which in turn drives the steam turbine generator set to generate electricity. After releasing the heat, the reactor coolant is sent back to the core by the main pump for reheating, and then enters the steam generator, and the cycle repeats.

[0062] The main equipment of the primary circuit includes reactor, main pump, steam generator, pressurizer, etc. In order to ensure the normal operation of the primary circuit and reactor, a series of auxiliary systems are also equipped, such as chemical and volume control system (RCV for short), reactor boron and water supply system (REA for short), main feed water flow control system (ARE for short) and chemical and volume control system volume control box (VCT for short).

[0063] In order to solve the technical problem that it is difficult to measure the heat loss power of the primary circuit of a nuclear power plant in the prior art, the present invention provides a method for measuring the heat loss power of the primary circuit of a nuclear power plant, by determining various influencing factors of the heat input and heat output of the primary circuit and configuring a specific unit state that meets the test requirements, thereby achieving accurate measurement of the heat loss power of the primary circuit. Figure 1 As shown, the method for measuring the heat dissipation loss power of the primary circuit of a nuclear power plant comprises the following steps:

[0064] S100: Adjust the unit operating status until the preset test conditions are met;

[0065] S200: Manually control the opening of the ARE water supply regulating valve to replenish the liquid level of the steam generator to the preset high liquid level. When the average temperature of the primary circuit is stable, manually close the ARE water supply regulating valve and the isolation valve, and record the start time of test data collection;

[0066] S300: During the test data collection, the GCT regulating valve opening is automatically controlled by setting the main steam pressure constant, and the primary circuit pressure, primary circuit average temperature and main steam pressure are maintained stable. When the steam generator liquid level drops to the preset low liquid level, the test data collection is stopped, and the end time of the test data collection is recorded;

[0067] S400: respectively obtain the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test;

[0068] S500: obtain the thermal power output from the main pump heat shield cooling water, RCV downstream heat exchanger, primary circuit leakage and steam generator from the primary circuit during the test;

[0069] S600: According to each of the thermal powers input to the primary circuit and each of the thermal powers output from the primary circuit, the heat dissipation loss power of the primary circuit is calculated by using the law of conservation of energy.

[0070] It should be noted that, in this embodiment, since the average primary circuit temperature of the hot shutdown platform and the full power platform of the nuclear power plant is basically close, the primary circuit heat dissipation loss power measurement test can be performed on the hot shutdown platform during the hot function test before the commercial operation of the nuclear power plant. In addition, in order to protect personnel, prevent equipment damage, and obtain effective test results, it is necessary to clarify the test precautions in advance, and the test precautions include the following:

[0071] Before the test, a test area must be established and no unauthorized personnel are allowed to enter or leave;

[0072] When operating electrical panels of 380V and above, strictly abide by the supervision system;

[0073] During the test, other experiments that may cause transient changes in the unit status are not allowed;

[0074] During the test, if the containment box is automatically replenished, the replenishment amount must be included in the calculation of primary circuit leakage;

[0075] During the test, it is prohibited to add lithium hydroxide, hydrazine, and hydrogen peroxide;

[0076] During the test, there is no sampling or drainage operation in the primary circuit;

[0077] To avoid the termination of the test due to deterioration of the steam generator water quality during the test, the steam generator water quality should be controlled to the best possible level before the test;

[0078] During the test, no changes to the status of the reactor building ventilation system are allowed;

[0079] During the test, the equipment cooling water temperature of the nuclear island equipment cooling water system (RRI) must be kept stable, with an allowable fluctuation range of ±0.5℃;

[0080] The following will discuss in detail the steps of the method for measuring the heat dissipation loss power of the primary circuit of the above-mentioned nuclear power plant.

[0081] First, step S100 is executed, that is, the operating state of the unit is adjusted until the preset test conditions are met.

[0082] It should be noted that, in this embodiment, the preset test conditions include: the nuclear reactor is in hot shutdown mode, the primary circuit pressure, the primary circuit average temperature and the main steam pressure are within the preset range, the main steam generated by the steam generator is discharged to the condenser through the GCT system, the main pump shaft seal is refluxed to the RCV system, and the RCV downstream flow to the TEP system coolant storage tank and the degassing pipeline has been isolated, the control channels of the regulator pressure, regulator liquid level and steam generator liquid level are in automatic mode, and the steam generator liquid level alarm signal and the action signal for triggering protection have been forcibly set, the steam generator secondary side sampling pipeline has been isolated, and the steam generator sewage is closed, the RCV control box liquid level has been replenished to the preset height, and the REA system is placed in automatic replenishment mode, and the water supply regulating valve from the ARE system to the steam generator is placed in manual control mode.

[0083] Specifically, in this embodiment, the primary circuit pressure is about 15.4 MPa.g, the primary circuit average temperature is about 295°C, and the deviation is ±2°C, the main steam pressure is about 7.9 MPa.g. It is worth noting that the pressure unit MPa.g refers to the gauge pressure, not the absolute pressure; the three main pumps are in normal operation. It should be noted that in this embodiment, the number of main pumps of the RCP system is three. Of course, in other embodiments, the number of main pumps of the RCP system can be 2, 4 or other numbers; the main steam generated by the steam generator is all passed through The main steam bypass system (GCT for short) discharges to the condenser; the main pump shaft seal returns to the chemical and volumetric control system (RCV for short); the operating status of the chemical and volumetric control system (RCV) includes: one RCV charging pump is in operation, one RCV downstream heat exchanger is in operation, and the RCV downstream flow to the coolant storage and treatment system (TEP for short) degassing pipeline has been isolated; the control channels of the primary circuit regulator pressure, the primary circuit regulator liquid level and the steam generator liquid level are in automatic mode; the secondary side sampling pipeline of the steam generator has been isolated; the steam generator blowdown has been closed.

[0084] In addition, in order to prevent the protection action from being triggered during the increase or decrease of the liquid level of the three steam generators, the liquid level alarm signals and the action signals for triggering the protection of the three steam generators should be forcibly set to ensure that the alarm and protection action will not be triggered during the test.

[0085] It should be noted that, in this embodiment, the number of the steam generators is consistent with the number of the RCP main pumps and corresponds to each other. The RCP system includes three loops, each loop including one RCP main pump and one steam generator.

[0086] Next, step S200 is executed, i.e., the opening of the ARE water supply regulating valve is manually controlled to replenish the liquid level of the steam generator to a preset high liquid level. When the average temperature of the primary circuit is stable, the ARE water supply regulating valve and the isolation valve are manually closed, and the start time of the test data collection is recorded;

[0087] Next, step S300 is executed, that is, during the test data collection, the GCT regulating valve opening is automatically controlled by setting the main steam pressure constant, and the primary circuit pressure, the primary circuit average temperature and the main steam pressure are maintained stable. When the steam generator liquid level drops to the preset low liquid level, the test data collection is stopped, and the end time of the test data collection is recorded.

[0088] It should be noted that, in this embodiment, the test is stopped when the liquid level of the steam generator drops to a preset low liquid level, and the water supply regulating valve and the isolation valve from the ARE system to the steam generator are reopened, and the water supply regulating valve and the isolation valve from the ARE system to the steam generator are placed in automatic control mode.

[0089] Specifically, the unit status needs to be checked and confirmed before the test data is formally collected. The operator checks and confirms whether the chemical and volume control system (RCV), reactor boron and water supply system (REA), main feed water flow control system (ARE), and reactor coolant system (RCP) meet the preset test conditions through the nuclear power digital instrumentation and control system (DCS), and performs correction operations as needed to meet the test conditions. In this embodiment, the REA system is used to replenish the liquid level of the RCV control tank in the manual replenishment mode, so that the liquid level of the RCV control tank is raised to slightly below 2m, and then the REA system is placed in the automatic replenishment mode. At the same time, the water supply regulating valve from the ARE system to the steam generator is placed in the manual control mode, and the opening of the water supply regulating valve is controlled to raise the liquid level of the steam generator to nearly 16.17m. When the average temperature of the primary circuit is stable, manually close the water supply regulating valve and isolation valve from the ARE system to the steam generator. After the above valves are closed, start collecting test data and record the start time t1 of test data collection. Use the DCS system to monitor the steam generator liquid level drop process in real time, and check that the parameters such as the primary circuit pressure, primary circuit average temperature, main steam pressure, and RRI cooling water temperature remain stable. When the steam generator liquid level drops to about 14m, stop the test data collection and record the end time t2 of the test data collection. At the same time, open the water supply regulating valve and isolation valve from the ARE system to the steam generator, set the water supply regulating valve to automatic control mode, resume steam generator blowdown, resume steam generator secondary side sampling, and cancel the steam generator liquid level signal force.

[0090] Next, step S400 is executed to respectively obtain the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test.

[0091] In an exemplary embodiment of the present application, see Figure 2 As shown, in step S400, the heat power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test is obtained respectively, further comprising the following steps:

[0092] S410: respectively acquiring test data of the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test;

[0093] S420: Obtaining the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit voltage stabilizer according to the test data.

[0094] In an exemplary embodiment of the present application, see Figure 3As shown, in step S410, the test data of the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator are respectively obtained during the test, further comprising the following steps:

[0095] S411: Obtain the average motor power and motor efficiency of the three RCP main pumps during the test;

[0096] S412: Obtaining the average motor power and motor efficiency of the RCV pump during the test;

[0097] S413: Obtain the opening setting value of each electric heater of the primary circuit voltage stabilizer and the average value of the actual power supply voltage during the test.

[0098] It should be noted that, in this embodiment, the motor power of each main pump is measured multiple times by the electrical panel, and the average motor power of the three main pumps is obtained by calculation. Similarly, the motor power of the RCV pump is measured multiple times by the electrical panel, and the average motor power of the RCV pump is obtained by calculation.

[0099] In an exemplary embodiment of the present application, see Figure 4 As shown, in step S420, according to the test data, the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator is obtained, further comprising the following steps:

[0100] S421: Multiply the average motor power of the three RCP main pumps by the motor efficiency and then sum them up to obtain the thermal power input by the RCP main pump to the primary circuit;

[0101] S422: multiplying the average motor power of the RCV pump by the motor efficiency to obtain the thermal power input by the RCV pump to the primary circuit;

[0102] S423: Calculate the power of each electric heater according to the opening setting value of each electric heater of the primary circuit regulator and the average value of the actual power supply voltage, and sum the power of each electric heater to obtain the thermal power input by the electric heater of the regulator to the primary circuit.

[0103] Specifically, during the test data collection period, the electric power of the three RCP main pumps was measured four times respectively, and the average value of the electric power measured by the four electrical panels was multiplied by the motor efficiency and then summed to obtain the thermal power W input by the three RCP main pumps to the primary circuit. RCPpumps :

[0104]

[0105] Where i represents the number of loops; W RCPpump-i It represents the power of the RCP main pump of the i-th loop, in kW.

[0106] During the test data collection period, the electric power of the RCV pump in the running column was measured 4 times, and the average value of the electric power measured by the electrical panel 4 times was multiplied by the motor efficiency to obtain the thermal power W input by the RCV pump to the primary circuit. RCVpump , unit is kW.

[0107] During the test data collection period, the opening setting values ​​of each electric heater of the voltage regulator and the average value of the actual power supply voltage of each electric heater are counted respectively, and the power of the i-th group of proportional electric heaters when the power supply voltage is 380V is queried. According to the opening setting values ​​of each electric heater, the average value of the actual power supply voltage and the power of the i-th group of proportional electric heaters when the power supply voltage is 380V, the power of each electric heater is calculated, and the power of each electric heater of the voltage regulator is summed to obtain the thermal power W input by the electric heater of the voltage regulator to the primary circuit. Heaters :

[0108]

[0109] Where i represents the number of loops; X represents the proportional electric heater opening setting value, %; W 380 Indicates the power of the i-th group of proportional electric heaters when the supply voltage is 380V, kW; U test Indicates the actual power supply voltage of the proportional electric heater, V; W Heaters-i Represents the power of the i-th group of proportional electric heaters, kW.

[0110] Then, step S500 is executed to respectively obtain the thermal power output from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test.

[0111] In an exemplary embodiment of the present application, see Figure 5 As shown, in step S500, the heat power output from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test is obtained respectively, further comprising the following steps:

[0112] S510: respectively obtain the test data of the main pump heat shield cooling water, RCV downstream heat exchanger, primary circuit leakage and steam generator during the test;

[0113] S520: According to the test data, the thermal power outputted from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator is obtained.

[0114] In an exemplary embodiment of the present application, see Figure 6As shown, in step S510, the test data of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test are respectively obtained, further comprising the following steps:

[0115] S511: respectively obtain the fluid inlet pressure, inlet and outlet temperature and flow rate on the RRI side of the main pump heat shield during the test;

[0116] S512: respectively obtaining the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RCV side of the RCV downstream heat exchanger and the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RRI side during the test;

[0117] S513: obtaining the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply amount, boric acid pressure, boric acid temperature, desalted water supply amount, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start and end time of test data collection respectively;

[0118] S514: respectively obtaining the steam generator liquid level at the start time of test data collection and the steam generator liquid level and steam generator pressure at the end time of test data collection.

[0119] It should be noted that when performing each data measurement, if there are multiple measuring points, it is necessary to measure the data of the multiple measuring points at the same time and calculate the average value thereof.

[0120] In an exemplary embodiment of the present application, see Figure 7 As shown, in step S520, according to the test data, the thermal power output of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator from the primary circuit is obtained, further comprising the following steps:

[0121] S521: Calculate the thermal power output of the main pump heat shield cooling water from the primary circuit according to the inlet pressure, inlet and outlet temperatures and flow rate of the fluid on the RRI side of the main pump heat shield;

[0122] S522: Calculate the thermal power output from the primary circuit of the RCV downstream heat exchanger according to the inlet pressure, inlet and outlet temperatures, and flow rate of the fluid on the RCV side of the operating RCV downstream heat exchanger and the inlet pressure, inlet and outlet temperatures, and flow rate of the fluid on the RRI side;

[0123] S523: according to the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply amount, boric acid pressure, boric acid temperature, desalted water supply amount, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start time and end time of test data collection, calculate and obtain the thermal power output from the primary circuit by the leakage of the primary circuit;

[0124] S524: Calculate the thermal power output of the steam generator from the primary circuit according to the steam generator liquid level at the start time of the test data collection and the steam generator liquid level and steam generator pressure at the end time of the test data collection.

[0125] Specifically, during the test data collection period, the average inlet pressure, average inlet temperature, average outlet temperature, and average flow rate of the RRI side of the heat shield cooling water of the three main pumps were counted respectively, and the thermal power W output from the primary circuit of the heat shield cooling water of the main pump was calculated based on these test data. TBs :

[0126]

[0127] W TB-i =Q m-i ×(h out-i -h in-i )

[0128]

[0129] Where i represents the number of loops; Q m-i represents the mass flow rate of the heat shield cooling water of the main pump of the i-th loop, corrected by the actual density, kg / s; Q i represents the flow rate of the heat shield cooling water of the main pump of the i-th loop, m 3 / h;h in-i represents the inlet enthalpy of the heat shield cooling water of the main pump of the i-th loop, obtained according to the inlet temperature and pressure of the heat shield cooling water, kJ / kg; h out-i represents the outlet enthalpy of the heat shield cooling water of the main pump of the i-th loop, obtained according to the outlet temperature and pressure of the heat shield cooling water, kJ / kg; ρ TB It represents the actual density of the heat shield cooling water of the main pump of the i-th loop, which is obtained according to the outlet temperature and pressure of the heat shield cooling water, kg / m 3 ρ TB-design represents the design density of the heat shield cooling water of the main pump of the i-th loop, kg / m 3 ; W TB-i It represents the thermal power output from the primary circuit by the heat shield cooling water of the main pump of the i-th loop, kW.

[0130] During the test data collection period, the average fluid inlet pressure, inlet temperature, outlet temperature and flow rate of the RCV side and RRI side of the RCV downstream heat exchanger were calculated respectively. Based on these test data, the thermal power W output from the primary circuit of the RCV downstream heat exchanger during the test period was calculated. RCV / RRI :

[0131]

[0132] Among them, Q m-RCV Indicates the mass flow rate on the RCV side of the downstream heat exchanger, corrected using actual density, kg / s; Q RCV Indicates the average value of the flow rate measured on the RCV side, t / h; Q m-RRI Indicates the mass flow rate on the RRI side of the downstream heat exchanger, corrected using actual density, kg / s; Q RRI Indicates the flow rate measured on the RRI side of the downstream heat exchanger, t / h; h in-RCV Indicates the inlet enthalpy value of the RCV side of the downstream heat exchanger, kJ / kg; h out-RCV Indicates the outlet enthalpy value of the RCV side of the downstream heat exchanger, kJ / kg; h in-RRI Indicates the inlet enthalpy value of the downstream heat exchanger RRI side, kJ / kg; h out-RRI Indicates the outlet enthalpy of the RRI side of the downstream heat exchanger, kJ / kg; ρ RCV Indicates the actual density of the fluid on the RCV side, which is obtained based on the outlet temperature and outlet pressure of the RCV side of the downstream heat exchanger, kg / m 3 ρ RCV-design Indicates the design density of the fluid on the RCV side, 994.6kg / m 3 ρ RRI Indicates the actual density of the fluid on the RRI side of the downstream heat exchanger, which is obtained based on the outlet temperature and outlet pressure of the RRI side of the downstream heat exchanger, kg / m 3 ρ RRI-design Indicates the design density of the fluid on the RRI side of the downstream heat exchanger, 962.6kg / m 3 .

[0133] According to the changes in the primary circuit pressurizer liquid level, RCV control box liquid level, boric acid supply and desalted water supply from the test data collection start time t1 to the test data collection end time t2, the primary circuit leakage flow is calculated, the primary circuit coolant enthalpy is obtained through the water vapor property table according to the primary circuit pressure and the primary circuit average temperature, the environmental water enthalpy in the containment is obtained through the water vapor property table according to the environmental temperature in the containment and the pressure in the containment, and the thermal power W output from the primary circuit by the primary circuit leakage is calculated according to the primary circuit leakage flow, the primary circuit coolant enthalpy and the environmental water enthalpy in the containment. Leak :

[0134] W Leak =Q Leak ×(h RCP -h HJ )

[0135]

[0136] Among them, Q Leak Indicates the leakage flow rate of a circuit, kg / s; h RCP Indicates the enthalpy value of the primary coolant, according to the primary pressure P RCP and the average temperature of the primary circuit T RCP Get, kJ / kg; h HJ It indicates the enthalpy of the water in the containment environment, according to the pressure inside the containment Pcontainment and the average temperature of the primary circuit T RCP Get, kJ / kg; L VCT-1 Indicates the liquid level of the control box at time t1, m; L VCT-2 Indicates the liquid level of the control box at time t2, m; S VCT Indicates the cross-sectional area of ​​the control box. The inner diameter of the control box is 2.4m and the cross-sectional area is 4.52m 2 ρ VCT Indicates the density of the liquid in the control box, kg / m 3 ; L PZR-1 Indicates the liquid level of the regulator at time t1, m; L PZR-2 Indicates the liquid level of the regulator at time t2, m; S PZR Indicates the cross-sectional area of ​​the stabilizer. The inner diameter of the stabilizer is 2.688m and the cross-sectional area is 5.67m 2 ρ PZR Indicates the density of the liquid in the stabilizer, kg / m 3 ; V BA-1 Indicates the amount of boric acid supplied at time t1, m 3 ; V BA-2 Indicates the amount of boric acid supplied at time t2, m 3 ρ BA Indicates the density of boric acid, kg / m 3 ; V DW-1 Indicates the amount of desalted water supplied at time t1, m 3 ; V DW-2 Indicates the amount of desalted water supplied at time t2, m 3 ρ DW Indicates the density of desalted water, kg / m 3 .

[0137] Record the average liquid level of each steam generator at time t1 (m), the average liquid level of each steam generator at time t2 (m), and the average pressure of each steam generator from the start time t1 to the end time t2 (MPa.g). The thermal power W output from the primary circuit of the steam generator SGs :

[0138]

[0139] Where i represents the number of loops; W SG-i It represents the thermal power output from the primary circuit of the i-th loop steam generator, kW; M i Indicates the mass of water reduced by evaporation in the steam generator of the i-th loop, kg; h s-i Indicates the saturated steam enthalpy value of the steam generator of the i-th loop, kJ / kg; obtained by looking up the water vapor property table based on the average pressure of the steam generator. h l-i Indicates the saturated water enthalpy value of the steam generator of the i-th loop, kJ / kg; obtained by looking up the water vapor property table according to the average pressure of the steam generator. t2-t1 indicates the time interval from time t1 to time t2, s; ρ i Indicates the saturated water density of the steam generator in the i-th loop, kg / m 3 ; Obtained from the water vapor properties table based on the average steam generator pressure. ΔV i represents the volume of water evaporated by the steam generator in loop i, m 3 ; Calculated based on the steam generator cross-sectional area and liquid level changes.

[0140] Finally, step S600 is performed, that is, according to each of the thermal powers input to the primary circuit and each of the thermal powers output from the primary circuit, the heat dissipation loss power of the primary circuit is calculated using the law of conservation of energy.

[0141] In an exemplary embodiment of the present application, the sum of the thermal powers input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator is subtracted from the sum of the thermal powers output from the primary circuit by the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator to obtain the heat dissipation loss power of the primary circuit.

[0142] Specifically, according to the heat power W input by the RCP main pump to the primary circuit RCPPumps , RCV pump input heat power W to the primary circuit RCVPump , the thermal power W input by the voltage stabilizer heater to the primary circuit Heaters 、The thermal power output of the steam generator from the primary circuit W SGs 、The thermal power W output from the primary circuit of the RCV downstream heat exchanger RCV / RRI , primary circuit leakage heat power output from primary circuit W Leak , calculate the heat loss power W of a circuit HL The heat dissipation loss power of the first circuit is W HL The calculation can be expressed as follows:

[0143] W HL =W RCPpumps +WRCVpump +W Heaters -W SGs -W RCV / RRI -W TBs -W Leak

[0144] Among them, W HL Indicates the power loss of heat dissipation in a circuit, kW; W RCPpumps Indicates the thermal power input by the RCP main pump to the primary circuit, kW; W RCVpump Indicates the thermal power input by the RCV pump to the primary circuit, kW; W Heaters Indicates the thermal power input to the primary circuit by the voltage stabilizer electric heater, kW; W SGs Indicates the thermal power output of the steam generator from the primary circuit, kW; W RCV / RRI Indicates the thermal power output from the primary circuit of the RCV downstream heat exchanger, kW; W TBs Indicates the heat power output of the main pump heat shield cooling water from the primary circuit, kW; W Leak Indicates the thermal power output from a primary circuit due to leakage from a primary circuit, kW.

[0145] In summary, the present invention provides a method for measuring the power loss of heat dissipation in a primary circuit of a nuclear power plant. The method adjusts the operating state of the unit until the preset test conditions are met, manually controls the opening of the ARE water supply regulating valve to replenish the liquid level of the steam generator to a preset high liquid level, manually closes the ARE water supply regulating valve and the isolation valve when the average temperature of the primary circuit is stable, and records the start time of the test data acquisition. During the test data acquisition, the opening of the GCT regulating valve is automatically controlled by setting the main steam pressure constant, and the primary circuit pressure, the primary circuit average temperature and the main steam pressure are maintained stable. When the liquid level of the steam generator drops to a preset low liquid level, the test data acquisition is stopped, and the end time of the test data acquisition is recorded. The thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test is respectively obtained, and the thermal power output from the primary circuit by the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator during the test is respectively obtained. According to the thermal power input to each of the primary circuits and the thermal power output from each of the primary circuits, the heat dissipation loss power of the primary circuit is calculated using the law of conservation of energy. The method determines various influencing factors of heat input and heat output of a primary circuit, and configures a specific unit state that meets the test requirements to achieve accurate measurement of the heat dissipation loss power of a primary circuit. The measurement process is relatively simple, which makes up for the difficulty in measuring the heat dissipation loss power of a primary circuit of a nuclear power plant in the prior art.

[0146] The above embodiments are merely illustrative of the principles and effects of the present invention, and are not intended to limit the present invention. Anyone familiar with the art may modify or alter the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or alterations made by a person of ordinary skill in the art without departing from the spirit and technical concept disclosed by the present invention shall still be covered by the claims of the present invention.

Claims

1. A method for measuring the heat dissipation loss power of a nuclear power plant primary circuit, characterized in that: include: Adjust the unit operating status until the preset test conditions are met; Manually control the opening of the ARE water supply regulating valve to replenish the liquid level of the steam generator to the preset high liquid level. When the average temperature of the primary circuit is stable, manually close the ARE water supply regulating valve and the isolation valve, and record the start time of test data collection; During the test data collection, the GCT regulating valve opening is automatically controlled by setting the main steam pressure constant, and the primary circuit pressure, primary circuit average temperature and main steam pressure are maintained stable. When the steam generator liquid level drops to the preset low liquid level, the test data collection is stopped and the end time of the test data collection is recorded; Obtain the thermal power input to the primary circuit by the RCP main pump, RCV pump and the electric heater of the primary circuit regulator during the test; The thermal power output from the main pump heat shield cooling water, RCV downflow heat exchanger, primary circuit leakage and steam generator from the primary circuit during the test is obtained respectively; The heat dissipation loss power of the primary circuit is calculated by utilizing the law of conservation of energy according to the heat power input to the primary circuit and the heat power output from the primary circuit.

2. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 1, characterized in that: The preset test conditions include: The nuclear reactor is in hot shutdown mode; The primary circuit pressure, primary circuit average temperature and main steam pressure are within the preset range; The main steam generated by the steam generator is discharged to the condenser through the GCT system; The main pump shaft seal returns to the RCV system, and the RCV downflow to the TEP system coolant storage tank and degassing pipeline has been isolated; The control channels of the primary circuit regulator pressure, primary circuit regulator liquid level and steam generator liquid level are in automatic mode, and the steam generator liquid level alarm signal and the action signal for triggering protection have been forcibly set; The steam generator secondary sampling line has been isolated and the steam generator blowdown is closed; The liquid level in the RCV control tank has been filled to the preset height, and the REA system is in automatic replenishment mode; The water supply regulating valve from the ARE system to the steam generator is placed in manual control mode.

3. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 1, characterized in that: Also includes: When the liquid level of the steam generator drops to the preset low liquid level, the test is stopped, and the water supply regulating valve and the isolation valve from the ARE system to the steam generator are reopened, and the water supply regulating valve and the isolation valve from the ARE system to the steam generator are placed in automatic control mode.

4. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 1, characterized in that: The heat power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit voltage stabilizer during the test is obtained respectively, including: Acquire test data of the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator during the test respectively; According to the test data, the thermal power input to the primary circuit by the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator is obtained.

5. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 4, characterized in that: The test data of the RCP main pump, the RCV pump and the electric heater of the primary circuit regulator are obtained respectively during the test, including: Obtain the average motor power and motor efficiency of the three RCP main pumps during the test; Obtain the average motor power and motor efficiency of the RCV pump during the test; Obtain the opening setting value of each electric heater of the primary circuit voltage stabilizer and the average actual power supply voltage during the test.

6. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 5, characterized in that: The method of obtaining the thermal power input to the primary circuit by the electric heater of the RCP main pump, the RCV pump and the primary circuit voltage stabilizer according to the test data includes: The average motor power of the three RCP main pumps is multiplied by the motor efficiency and then summed to obtain the thermal power input by the RCP main pump to the primary circuit; Multiplying the average motor power of the RCV pump by the motor efficiency to obtain the thermal power input by the RCV pump to the primary circuit; According to the opening setting value of each electric heater of the primary circuit regulator and the average actual power supply voltage, the power of each electric heater is calculated respectively, and the power of each electric heater is summed to obtain the thermal power input by the electric heater of the regulator to the primary circuit.

7. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 1, characterized in that: The heat power output of the main pump heat shield cooling water, RCV downstream heat exchanger, primary circuit leakage and steam generator from the primary circuit during the test is obtained respectively, including: Obtain the test data of the main pump heat shield cooling water, RCV downflow heat exchanger, primary circuit leakage and steam generator during the test; According to the test data, the thermal power output from the primary circuit of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator is obtained.

8. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 7, characterized in that: The test data of the main pump heat shield cooling water, RCV downstream heat exchanger, primary circuit leakage and steam generator during the test are obtained respectively, including: The fluid inlet pressure, inlet and outlet temperatures and flow rate of the main pump heat shield RRI side during the test were obtained respectively; Obtain the fluid inlet pressure, inlet and outlet temperature, flow rate of the RCV side of the RCV downstream heat exchanger and the fluid inlet pressure, inlet and outlet temperature, flow rate of the RRI side during the test; Obtain the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply, boric acid pressure, boric acid temperature, desalted water supply, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start and end time of test data collection respectively; respectively obtaining the steam generator liquid level at the start time of test data collection and the steam generator liquid level and steam generator pressure at the end time of test data collection; If there are multiple measurement points in the measurement data, the average value of the multiple measurement points at the same time is calculated.

9. The method for measuring the heat dissipation loss power of a nuclear power plant primary circuit according to claim 8, characterized in that: The method of obtaining the heat output of the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator from the primary circuit based on the test data includes: According to the inlet pressure, inlet and outlet temperature and flow rate of the fluid on the RRI side of the main pump heat shield, the thermal power output of the main pump heat shield cooling water from the primary circuit is calculated; Calculate the thermal power output of the RCV downstream heat exchanger from the primary circuit according to the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RCV side of the operating RCV downstream heat exchanger and the inlet pressure, inlet and outlet temperature, flow rate of the fluid on the RRI side; According to the primary circuit pressurizer liquid level, RCV control box liquid level, RCV control box pressure, RCV control box temperature, steam generator liquid level, boric acid supply, boric acid pressure, boric acid temperature, desalted water supply, desalted water pressure, desalted water temperature, primary circuit pressure, primary circuit average temperature and containment environment temperature at the start and end time of test data collection, the thermal power output from the primary circuit by the leakage of the primary circuit is calculated; The thermal power output of the steam generator from the primary circuit is obtained by calculation according to the steam generator liquid level at the start time of the test data collection and the steam generator liquid level and the steam generator pressure at the end time of the test data collection.

10. The method for measuring the power loss of a primary circuit of a nuclear power plant according to claim 1, characterized in that: The heat loss power of the primary circuit is calculated by using the law of conservation of energy according to the heat power input to the primary circuit and the heat power output from the primary circuit, including: The sum of the thermal powers input to the primary circuit by the RCP main pump, RCV pump and the electric heater of the primary circuit regulator is subtracted from the sum of the thermal powers output from the primary circuit by the main pump heat shield cooling water, the RCV downstream heat exchanger, the primary circuit leakage and the steam generator to obtain the heat dissipation loss power of the primary circuit.

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