Generated power testing device and method for small nuclear power generation system
By designing a power generation testing device, electrical energy is converted into thermal energy and thermal energy parameters are measured using sensors. This solves the problem of inaccurate measurement of unstable power generation quality in small nuclear power generation systems and enables accurate calculation of power generation.
Patent Information
- Application Number
- CN202511215628.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-08-28
- Publication Date
- 2025-11-21
AI Technical Summary
The unstable power generation quality of the small nuclear power generation system prototype leads to inaccurate power generation measurement, and existing technologies make it difficult to obtain accurate voltage and current RMS values and calculate power generation.
Design a power generation testing device that uses a deionized pure water tank, a coil-type electric heater, and a heat exchanger to convert electrical energy into heat energy. Measure the heat energy parameters using temperature, pressure, and flow sensors, and calculate the power generation by combining the law of conservation of energy.
It enables accurate testing of the power generation capacity of small nuclear power generation systems, reduces heat loss, and improves measurement accuracy.
Smart Images
Figure CN120993034A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of power testing technology, and in particular to a power generation testing device and method for small nuclear power generation systems. Background Technology
[0002] The statements in this section are merely background information related to the present invention and do not necessarily constitute prior art.
[0003] Small nuclear power generation systems generate electricity through small nuclear reactors, which are small and simple nuclear power generation and heat production units. Currently, small nuclear power generation systems have broad application prospects in environments such as space, land, and sea.
[0004] Currently, the performance verification of such systems is mainly accomplished through experiments. However, due to the instability of the power generation quality (such as waveform and frequency) of the prototype in the system, the output voltage and current are not standard sine waves or DC currents. Based on this, when using ordinary voltage and current sensors to collect these non-standard voltage and current signals, it is difficult to obtain accurate effective values of voltage and current due to reasons such as incorrect acquisition frequency and difficulty in properly processing non-standard signals. Consequently, the calculation of the power generation of the prototype is also inaccurate. Summary of the Invention
[0005] To address the shortcomings of the prior art, this invention provides a power generation testing device and method for small nuclear power generation systems. Based on the relationship between electrical power and heat, a novel power generation testing device is designed. By using this device to test the power of the prototype in the system, the problem of inaccurate power generation measurement caused by the unstable power generation quality of the prototype in the small nuclear power generation system can be solved, thus achieving accurate power testing.
[0006] In a first aspect, the present invention provides a power generation testing device for small nuclear power generation systems.
[0007] A power generation testing device for small nuclear power generation systems includes a deionized pure water tank, a coil-type electric heater, and a heat exchanger. Among them, the coil-type electric heater is connected to the prototype of the small nuclear power generation system under test through a power supply cable, and is used to convert the electrical energy output by the prototype of the small nuclear power generation system into heat energy. Deionized purified water at a set temperature in the deionized purified water tank is pumped through pipes into a coil-type electric heater. After heat exchange, the deionized purified water carrying heat energy is heated to the set temperature through a heat exchanger and then flows back to the deionized purified water tank.
[0008] A further technical solution is that temperature, pressure, and flow sensors are installed on the inlet and outlet pipes of the coil-type electric heater, namely: a second temperature sensor, a second pressure sensor, and a second flow meter are installed at the outlet, and a first temperature sensor, a first pressure sensor, and a first flow meter are installed at the inlet; a third and a fourth temperature sensor are respectively installed in the outlet pipe of the heat exchanger and in the deionized pure water tank. The deionized pure water tank is connected to the coil-type electric heater through an inlet pipe. A water pump and a first inlet valve are sequentially installed on the inlet pipe. A return water pipe is installed between the water pump and the first inlet valve and connected to the deionized pure water tank. A first return water valve is installed on the return water pipe. The heat exchanger is connected to external cooling water through a cooling water inlet pipe and a cooling water return pipe. A second inlet valve and a second return valve are respectively installed on the cooling water inlet pipe and the cooling water return pipe.
[0009] In a further technical solution, the coil-type electric heater includes a metal tube and an insulating tube; In the small nuclear power generation system under test, the output cable of the prototype is connected to the metal wall at both ends of the metal pipe. Insulating pipes are sleeved on the outside of the connection between the metal pipe and the cable at both ends. The electrical energy is converted into heat energy on the outer shell of the metal pipe by a coil-type electric heater. Deionized pure water is pressurized by a water pump and flows through the inside of the metal pipe. The heat energy converted from electrical energy is carried out through heat exchange.
[0010] In a further technical solution, the metal pipe is a U-shaped bent pipe, and the outer wall of the metal pipe is wrapped with an insulation layer, which is used to prevent heat loss.
[0011] Secondly, the present invention provides a method for testing the power generation capacity of a small nuclear power generation system.
[0012] A method for testing the power generation capacity of a small nuclear power generation system, implemented based on the power generation capacity testing device proposed in the first aspect, includes: The prototype of the small nuclear power generation system under test was connected to the coil-type electric heater in the test system. At the same time, the prototype and the water pump were started, and temperature, pressure and flow data were acquired in real time. Adjust the first inlet valve and the first return valve to regulate the flow rate of pure water entering the coil-type electric heater, so that the flow rate of pure water meets the condition that the water in the heater does not vaporize. Adjust the second inlet valve and the second return valve to regulate the cooling water flow rate in the heat exchanger, so that the temperature of the pure water flowing out of the heat exchanger is always consistent with the temperature of the water in the deionized pure water tank. After the set running time, the test prototype was stopped, and the valve adjustment continued until the temperature, pressure, and flow rate of the pure water at the inlet and outlet of the coil-type electric heater were consistent, thus completing the test.
[0013] A further technical solution involves calculating the power output of the prototype of the small nuclear power generation system under test based on the data obtained during the testing process. The calculation formula is as follows: ; ; in, This indicates the real-time flow rate at the inlet of the coil-type electric heater. 、 These represent the real-time enthalpy values of the cooling water at the outlet and inlet of the coil-type electric heater, respectively. 、 These represent the start and end times of the test, respectively. T This indicates the running time of the prototype.
[0014] A further technical solution is that the enthalpy value of the cooling water at the outlet is obtained by looking up the physical property parameter table of the cooling water based on the temperature value measured by the second temperature sensor and the pressure value measured by the second pressure sensor. The enthalpy value of the cooling water at the inlet is obtained by referring to the physical property parameter table of the cooling water based on the temperature value measured by the first temperature sensor and the pressure value measured by the first pressure sensor.
[0015] A further technical solution is to use the calculated power value as the test power value. Test power value With pre-calibrated heat dissipation coefficient Calculations and corrections are performed to obtain the corrected power value; the correction formula is as follows: ; In the above formula, This indicates the corrected power value; Indicates the measured power value; This represents the pre-calibrated heat dissipation coefficient.
[0016] A further technical solution is to prevent vaporization under the condition that the current ambient pressure is greater than or equal to the saturated vapor pressure of the liquid at the current ambient temperature.
[0017] A further technical solution is to automatically adjust the first inlet valve and the first return valve based on the pressure values measured in real time by the first and second pressure sensors and the flow values measured in real time by the first and second flow meters, so that the two pressure values and the two flow values are the same. Based on the real-time temperature values measured by the third and fourth temperature sensors, the second inlet valve and the second return valve are automatically adjusted to ensure that the two temperature values are the same and both are the set temperature values.
[0018] The above one or more technical solutions have the following beneficial effects: 1. This invention provides a power generation testing device and method for small nuclear power generation systems. Based on the relationship between electrical power and heat, a novel power generation testing device is set up. This device is used to test the power of the prototype in the system. Through corresponding process methods, process flow, data processing methods, etc., the problem of inaccurate power generation measurement caused by the unstable power generation quality of the prototype in the small nuclear power generation system is solved, and accurate power testing is achieved.
[0019] 2. The power generation testing principle proposed in this invention is as follows: The electrical energy output by the prototype of the small nuclear power generation system is converted into the heat energy of a coil-type electric heater. The coil-type electric heater is externally insulated to avoid heat loss or dissipation, thereby avoiding errors in subsequent power calculations. Deionized cooling water is used as the cooling medium to remove the heat energy from the coil-type electric heater through heat conversion. Based on directly measured parameters such as the heater inlet and outlet temperatures, pressures, and flow rates, the heat exchange power of the inlet and outlet deionized water is calculated. On this basis, according to the law of conservation of energy, under steady-state conditions, the heat exchange power of the inlet and outlet deionized water is equal to the electrical power output by the prototype of the power generation system, thus accurately testing the power generation of the small nuclear power generation system.
[0020] Advantages of additional aspects of the invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention. Attached Figure Description
[0021] The accompanying drawings, which form part of this invention, are used to provide a further understanding of the invention. The illustrative embodiments of the invention and their descriptions are used to explain the invention and do not constitute an improper limitation of the invention.
[0022] Figure 1 This is an overall design drawing of the power generation testing device for small nuclear power generation systems according to an embodiment of the present invention; Figure 2 This is a schematic diagram of the power generation testing device according to an embodiment of the present invention; Figure 3 This is a schematic diagram of the structure of the coil-type electric heater in an embodiment of the present invention. Detailed Implementation
[0023] It should be noted that the following detailed descriptions are exemplary and are intended only to describe specific embodiments and to provide further explanation of the invention, and are not intended to limit the scope of exemplary embodiments of the invention. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains. Furthermore, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.
[0024] Example 1 This embodiment provides a power generation testing device for small nuclear power generation systems, such as... Figure 1 As shown, it includes a deionized pure water tank, a coil-type electric heater, a heat exchanger, a water pump, a valve assembly, a pressure transmitter (i.e., a pressure sensor), a temperature transmitter (i.e., a temperature sensor), a flow meter, etc. Figure 2 As shown, the coil-type electric heater is equipped with a terminal block, which is connected to the prototype of the small nuclear power generation system under test via a power supply cable. It is used to convert the electrical energy output by the prototype of the small nuclear power generation system into heat energy. The deionized pure water tank, the coil-type electric heater, and the heat exchanger are connected in sequence through pipes to form a loop. The deionized pure water in the deionized pure water tank circulates in this loop.
[0025] Based on the aforementioned power generation testing device for small nuclear power generation systems, the entire process flow is as follows: (1) The electrical energy output by the prototype of the small nuclear power generation system is transmitted to the coil-type electric heater via cable. The coil-type electric heater has a metal shell inside. The electrical energy is transmitted to both ends of the length direction of the metal shell of the coil-type electric heater via cable. Voltage is generated at both ends of the length direction of the metal shell of the coil-type electric heater, and current flows through the length direction of the metal shell, generating heat.
[0026] Preferred, such as Figure 3 As shown, the coil-type electric heater proposed in this embodiment includes a metal tube and an insulating tube. The output cable of the prototype in the small nuclear power generation system under test is connected to the metal walls at both ends of the metal tube. Insulating tubes are sleeved on the outside of the connection points between the metal tube and the cable to ensure that no current flows through the upstream and downstream equipment of the coil-type electric heater. In addition, the metal tube is a U-shaped bend. Setting it as a U-shape can effectively reduce flow resistance and thermal stress, thereby reducing heat dissipation and improving the durability and reliability of the metal tube. Moreover, the outer wall of the metal tube is wrapped with an insulation layer to further reduce heat dissipation, effectively prevent heat loss, and ensure the accuracy of subsequent power calculations. Through the above settings, the coil-type electric heater converts electrical energy into heat energy on the outer shell of the metal tube. Deionized pure water is pressurized by a water pump and flows through the inside of the metal tube, carrying the heat energy converted from electrical energy out through heat exchange.
[0027] (2) Deionized pure water at the set temperature in the deionized pure water tank enters the coil-type electric heater through the water pump via the pipeline. After the heat exchange is heated, the heat generated by the metal shell of the coil-type electric heater is carried away, and the deionized pure water is heated. Then, the deionized pure water carrying heat energy (i.e., the heated deionized pure water) carries away the heat through the cooling water in the heat exchanger. After the heat exchange reaches the set temperature, it flows back to the deionized pure water tank.
[0028] like Figure 1 As shown, temperature, pressure, and flow sensors are installed on the inlet and outlet pipes of the coil-type electric heater. Specifically, a second temperature sensor, a second pressure sensor, and a second flow meter are installed at the outlet, and a first temperature sensor, a first pressure sensor, and a first flow meter are installed at the inlet. A third and a fourth temperature sensor are installed on the outlet pipe of the heat exchanger and inside the deionized pure water tank, respectively. The deionized pure water tank is connected to the coil-type electric heater through an inlet pipe. A water pump and a first inlet valve are installed sequentially on the inlet pipe. A return water pipe is installed between the water pump and the first inlet valve, connecting to the deionized pure water tank. A first return water valve is installed on the return water pipe. The heat exchanger is connected to external cooling water through a cooling water inlet pipe and a cooling water return pipe. A second inlet valve and a second return water valve are installed on the cooling water inlet pipe and the cooling water return pipe, respectively.
[0029] Example 2 This embodiment provides a method for testing the power generation capacity of a small nuclear power generation system, based on the power generation capacity testing system proposed in Embodiment 1, and specifically includes the following steps: Step S1: Connect the prototype of the small nuclear power generation system to be tested to the coil-type electric heater in the test system, and start the prototype and water pump at the same time to start the test, and acquire temperature, pressure and flow data in real time. Step S2: Adjust the first inlet valve and the first return valve to regulate the flow rate of pure water entering the coil-type electric heater, so that the flow rate of pure water meets the condition that the water in the heater does not vaporize; wherein, the condition that does not vaporize is: the current ambient pressure is greater than or equal to the saturated vapor pressure of the liquid at the current ambient temperature. Step S3: Adjust the second inlet valve and the second return valve to regulate the flow rate of cooling water in and out of the heat exchanger, so that the temperature of the pure water flowing out of the heat exchanger is always consistent with the temperature of the water in the deionized pure water tank; wherein, this temperature is actually the set temperature in the deionized pure water tank, and in this embodiment, the set temperature is set to 10°C subcooling. Step S4: After the set running time, stop the test prototype and continue adjusting the valves in steps S2 and S3 until the temperature, pressure, and flow rate of the purified water at the inlet and outlet of the coil-type electric heater are consistent, thus completing the test. In other words, the condition for reading the test results is that the temperature, pressure, and flow rate parameters of the deionized purified water at the inlet and outlet of the coil-type electric heater eventually reach a stable state.
[0030] In the power generation testing method proposed in this embodiment, steps S2 and S3 are actually two parallel steps. Furthermore, based on the data obtained during the testing process, the power output of the prototype of the small nuclear power generation system under test was calculated using the following formula: ; ; in, This indicates the real-time flow rate at the inlet of the coil-type electric heater. 、 These represent the start and end times of the test, respectively. T This indicates the running time of the prototype, i.e., the running time set above. 、 These represent the real-time enthalpy values of the cooling water at the outlet and inlet of the coil-type electric heater, respectively. These enthalpy values are obtained as follows: The enthalpy of the cooling water at the outlet is obtained by referring to the physical property parameter table of the cooling water based on the temperature value measured by the second temperature sensor and the pressure value measured by the second pressure sensor. The enthalpy of the cooling water at the inlet is obtained by referring to the physical property parameter table of the cooling water based on the temperature value measured by the first temperature sensor and the pressure value measured by the first pressure sensor.
[0031] Preferably, considering the heat dissipation problem during the heat transfer through the metal casing or metal pipe in the above test process, although the heat dissipation can be reduced to a certain extent by setting an insulation layer, some heat loss still occurs. To ensure the accuracy of the final power calculation, the calculated power value is used as the test power value. With pre-calibrated heat dissipation coefficient Calculations and corrections are performed to obtain a revised power value, making the power calculation more accurate. Specifically, the correction formula is as follows: ; In the formula, This indicates the corrected power value; Indicates the measured power value; This represents the pre-calibrated heat dissipation coefficient, which can be determined by the pre-calibration method before use.
[0032] Among them, the aforementioned pre-calibrated heat dissipation coefficient The method of obtaining it is: First, calibrate the device settings. Use known output power. The standard power supply was used to replace the prototype of the small nuclear power generation system under test. The standard power supply was connected to the coil-type electric heater to ensure that other components of the device, such as sensors, valves, and cooling systems, were the same as those in the actual test.
[0033] Secondly, system operation and data acquisition. The standard power supply and water pump were started, and the valves were adjusted to bring the system to a steady state. During the test, data such as flow rate, inlet and outlet temperature, and pressure were collected in real time using sensors.
[0034] Finally, the heat dissipation system is calculated and determined. Based on the above formula for calculating power generation, the measured power is calculated. And define the heat dissipation coefficient as This is used to calculate the system's actual heat energy conversion efficiency. .
[0035] Preferably, the final calibration value is obtained by taking the average of multiple calibration experiments (e.g., multiple experiments covering different power ranges) to ensure its applicability under different operating conditions. In subsequent actual tests, the correction formula can also be used... It is applied to measurement data to eliminate errors caused by heat loss and improve the accuracy of power calculation.
[0036] As another implementation, based on the pressure values measured in real time by the first and second pressure sensors and the flow values measured in real time by the first and second flow meters, the first inlet valve and the first return valve can be automatically adjusted so that the two pressure values and the two flow values are the same.
[0037] Specifically, the above automatic adjustment process is as follows: First, the control objective is clearly defined as follows: By adjusting the valve opening, the inlet and outlet of the coil-type electric heater meet the following requirements: and The pressure measured by the first pressure sensor is... The second pressure sensor measures the pressure as the input pressure. To output pressure, the first flow meter measures the flow rate. The second flow meter measures the flow rate as the input flow rate. For output flow.
[0038] Secondly, based on the control objectives defined above, a PID controller is used for closed-loop automatic adjustment. Specifically, the pressure error and flow error are defined as follows: , If the error exceeds the allowable range, valve adjustment is triggered; the valve opening is dynamically adjusted according to the error, wherein the opening of the inlet valve is adjusted as follows: Increase the opening of the inlet valve. The flow rate can be increased, and vice versa; the opening of the return water valve is adjusted as follows: Increase the opening of the return water valve It can reduce pressure, and vice versa.
[0039] The above method can achieve automatic adjustment of the first inlet valve and the first return valve, so that the two pressure values and the two flow values are the same.
[0040] Similarly, based on the real-time temperature values measured by the third and fourth temperature sensors, the second inlet valve and the second return valve can be automatically adjusted to ensure that both temperature values are the same and both are the set temperature values. The automatic adjustment process is as follows: First, the control objective is clearly defined as: by adjusting the valve opening, the water temperature at the heat exchanger outlet is controlled. The water temperature in the deionized pure water tank Same, satisfying: ,in, To set the temperature.
[0041] Secondly, based on the control objectives defined above, a PID controller is used for closed-loop automatic adjustment. Specifically, the temperature error is defined as: If the error exceeds the allowable range, valve adjustment is triggered; the valve opening is dynamically adjusted according to the error, wherein the opening of the inlet valve is adjusted as follows: Increase the opening of the inlet valve. This can increase the cooling water flow rate and enhance heat exchange capacity; the opening degree of the return water valve is adjusted as follows: Increase the opening of the return water valve It can reduce system back pressure, indirectly increase the cooling water circulation volume, and make the water tank temperature more uniform.
[0042] The above method enables automatic adjustment of the second inlet valve and the second return valve, ensuring that the two temperature values are the same.
[0043] By using the power generation testing device proposed in this embodiment to test the power of the prototype in the system, and through corresponding process methods, process flow, and data processing methods, the accurate power generation can be calculated and obtained, thus solving the problem of inaccurate power generation measurement caused by the unstable power generation quality of the prototype of the small nuclear power generation system.
[0044] The steps involved in the above embodiment two correspond to those in embodiment one. For specific implementation details, please refer to the relevant description section of embodiment one.
[0045] The above description is only a preferred embodiment of the present invention. Although the specific implementation of the present invention has been described in conjunction with the accompanying drawings, it is not intended to limit the scope of protection of the present invention. Those skilled in the art should understand that, based on the technical solution of the present invention, various modifications or variations that can be made by those skilled in the art without creative effort are still within the scope of protection of the present invention.
Claims
1. A power generation testing device for small nuclear power generation systems, characterized in that, Includes deionized pure water tank, coil electric heater, and heat exchanger; Among them, the coil-type electric heater is connected to the prototype of the small nuclear power generation system under test through a power supply cable, and is used to convert the electrical energy output by the prototype of the small nuclear power generation system into heat energy. Deionized purified water at a set temperature in the deionized purified water tank is pumped through pipes into a coil-type electric heater. After heat exchange, the deionized purified water carrying heat energy is heated to the set temperature through a heat exchanger and then flows back to the deionized purified water tank.
2. The power generation testing device for small nuclear power generation systems as described in claim 1, characterized in that, Temperature, pressure, and flow sensors are installed on the inlet and outlet pipes of the coil-type electric heater, namely: a second temperature sensor, a second pressure sensor, and a second flow meter are installed at the outlet, and a first temperature sensor, a first pressure sensor, and a first flow meter are installed at the inlet; a third and a fourth temperature sensor are installed on the outlet pipe of the heat exchanger and in the deionized pure water tank, respectively. The deionized pure water tank is connected to the coil-type electric heater through an inlet pipe. A water pump and a first inlet valve are sequentially installed on the inlet pipe. A return water pipe is installed between the water pump and the first inlet valve and connected to the deionized pure water tank. A first return water valve is installed on the return water pipe. The heat exchanger is connected to external cooling water through a cooling water inlet pipe and a cooling water return pipe. A second inlet valve and a second return valve are respectively installed on the cooling water inlet pipe and the cooling water return pipe.
3. The power generation testing device for small nuclear power generation systems as described in claim 1, characterized in that, The coil-type electric heater includes a metal tube and an insulating tube; In the small nuclear power generation system under test, the output cable of the prototype is connected to the metal wall at both ends of the metal pipe. Insulating pipes are sleeved on the outside of the connection between the metal pipe and the cable at both ends. The electrical energy is converted into heat energy on the outer shell of the metal pipe by a coil-type electric heater. Deionized pure water is pressurized by a water pump and flows through the inside of the metal pipe. The heat energy converted from electrical energy is carried out through heat exchange.
4. The power generation testing device for small nuclear power generation systems as described in claim 3, characterized in that, The metal pipe is a U-shaped bent pipe, and the outer wall of the metal pipe is wrapped with a heat insulation layer to prevent heat loss.
5. A method for testing the power generation capacity of a small nuclear power generation system, implemented based on the power generation capacity testing device according to any one of claims 1-4, characterized in that, include: The prototype of the small nuclear power generation system under test was connected to the coil-type electric heater in the test system. At the same time, the prototype and the water pump were started, and temperature, pressure and flow data were acquired in real time. Adjust the first inlet valve and the first return valve to regulate the flow rate of pure water entering the coil-type electric heater, so that the flow rate of pure water meets the condition that the water in the heater does not vaporize. Adjust the second inlet valve and the second return valve to regulate the cooling water flow rate in the heat exchanger, so that the temperature of the pure water flowing out of the heat exchanger is always consistent with the temperature of the water in the deionized pure water tank. After the set running time, the test prototype was stopped, and the valve adjustment continued until the temperature, pressure, and flow rate of the pure water at the inlet and outlet of the coil-type electric heater were consistent, thus completing the test.
6. The power generation testing method for small nuclear power generation systems as described in claim 5, characterized in that, Based on the data obtained during the test, the power output of the prototype of the small nuclear power generation system under test was calculated using the following formula: ； ； in, This indicates the real-time flow rate at the inlet of the coil-type electric heater. 、 These represent the real-time enthalpy values of the cooling water at the outlet and inlet of the coil-type electric heater, respectively. 、 These represent the start and end times of the test, respectively.
7. The power generation testing method for small nuclear power generation systems as described in claim 6, characterized in that, The enthalpy value of the cooling water at the outlet is obtained by referring to the physical property parameter table of the cooling water based on the temperature value measured by the second temperature sensor and the pressure value measured by the second pressure sensor. The enthalpy value of the cooling water at the inlet is obtained by referring to the physical property parameter table of the cooling water based on the temperature value measured by the first temperature sensor and the pressure value measured by the first pressure sensor.
8. The power generation testing method for small nuclear power generation systems as described in claim 6, characterized in that, The calculated power value is used as the test power value. Test power value With pre-calibrated heat dissipation coefficient Calculations and corrections are performed to obtain the corrected power value; the correction formula is as follows: ； In the above formula, This indicates the corrected power value; Indicates the measured power value; This represents the pre-calibrated heat dissipation coefficient.
9. The power generation test method for small nuclear power generation systems as described in claim 5, characterized in that, The condition under which vaporization does not occur is that the current ambient pressure is greater than or equal to the saturated vapor pressure of the liquid at the current ambient temperature.
10. The power generation testing method for small nuclear power generation systems as described in claim 5, characterized in that, Based on the real-time pressure values measured by the first and second pressure sensors and the real-time flow values measured by the first and second flow meters, the first inlet valve and the first return valve are automatically adjusted to make the two pressure values and the two flow values the same. Based on the real-time temperature values measured by the third and fourth temperature sensors, the second inlet valve and the second return valve are automatically adjusted to ensure that the two temperature values are the same and both are the set temperature values.