Method and system for detecting integrity of heat transfer tubes in high temperature gas-cooled reactor steam generators

Abstract

The present application proposes a method and system for detecting the integrity of heat transfer tubes in a high-temperature gas-cooled reactor steam generator. The method includes: sampling helium in a primary circuit of a nuclear power plant in a reactor power operation mode to obtain a first helium sample and a second helium sample; detecting the humidity value of the first helium sample and the impurity content of the second helium sample; obtaining a first detection result of the integrity of the heat transfer tubes in the high-temperature gas-cooled reactor steam generator based on the humidity value of the first helium sample and the impurity content of the second helium sample; performing a helium leak test on the heat transfer tubes in the high-temperature gas-cooled reactor steam generator in a shutdown overhaul mode to obtain a second detection result of the integrity of the heat transfer tubes in the high-temperature gas-cooled reactor steam generator; and ultimately determining the integrity of the heat transfer tubes in the high-temperature gas-cooled reactor steam generator based on the first and second detection results. The present application can promptly detect leaks in the heat transfer tubes and improve the accuracy of integrity detection.

Description

Technical Field

[0001] The present application relates to the field of nuclear power online detection technology, and in particular to a method and system for detecting the integrity of heat transfer tubes of a high-temperature gas-cooled reactor steam generator. Background Art

[0002] The high-temperature gas-cooled reactor is a fourth-generation nuclear power plant with inherent safety features and high thermal efficiency. Its steam generator is a heat exchange device that connects and isolates the primary and secondary circuits. It serves as a barrier to ensure the integrity of the primary circuit pressure boundary and prevents water or steam from the secondary circuit from entering the primary circuit, thereby performing nuclear safety functions.

[0003] The integrity of the steam generator heat transfer tubes is particularly important for the safe operation of nuclear power plants. Since the pressure of the secondary circuit of a nuclear power plant is much higher than that of the primary circuit, if a leak occurs in the steam generator heat transfer tubes, it may lead to serious consequences such as the introduction of reactivity, graphite corrosion, and pressure increase of the primary circuit system, endangering the safe operation of the unit. Summary of the Invention

[0004] The present application aims to solve one of the technical problems in the related art at least to a certain extent.

[0005] To this end, the first aspect of the present application proposes a method for detecting the integrity of a heat transfer tube of a high-temperature gas-cooled reactor steam generator, comprising:

[0006] In response to the nuclear power plant operating state being a reactor power operation mode, sampling helium in a primary circuit of the nuclear power plant to obtain a first helium sample and a second helium sample;

[0007] detecting a humidity value of the first helium sample and an impurity content of the second helium sample;

[0008] Obtaining a first detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator according to the humidity value of the first helium sample and the impurity content of the second helium sample;

[0009] In response to the nuclear power plant operating state being in a shutdown overhaul mode, performing a helium leak test on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second test result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator;

[0010] Based on the first test result and the second test result, the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator is finally determined.

[0011] In some embodiments of the present application, sampling the helium in the primary circuit of a nuclear power plant to obtain a first helium sample includes: sampling the helium in the primary circuit of the nuclear power plant at the outlet of a helium blower in the primary circuit of the nuclear power plant to obtain the first helium sample.

[0012] In some embodiments of the present application, detecting the humidity value of the first helium sample includes: sending the first helium sample to a humidity measuring device through a sampling pipe for measurement to obtain the humidity value of the first helium sample; after the humidity measuring device completes the measurement, returning the first helium sample to the helium blower inlet of the primary circuit, so as to utilize the pressure difference between the helium blower outlet and the helium blower inlet to maintain the gas circulation of the humidity measuring device.

[0013] In some embodiments of the present application, obtaining a first detection result of the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator based on the humidity value of the first helium sample and the impurity content of the second helium sample includes: comparing the humidity value of the first helium sample with a preset humidity threshold; comparing the impurity content of the second helium sample with a preset impurity content threshold; in response to the humidity value of the first helium sample being greater than the humidity threshold and / or the impurity content of the second helium sample being greater than the impurity content threshold, detecting that the heat transfer tube of the high-temperature gas-cooled reactor steam generator is leaking, and using the detection result of the leakage of the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the first detection result.

[0014] In some embodiments of the present application, the helium leak detection is performed on the heat transfer tube of the high-temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator, including: evacuating the secondary side of the high-temperature gas-cooled reactor steam generator and inflating and pressurizing the primary side of the high-temperature gas-cooled reactor steam generator with helium; performing helium content detection on the secondary side of the high-temperature gas-cooled reactor steam generator with a helium mass spectrometer to obtain a helium content value; comparing the helium content value with a preset helium content threshold; in response to the helium content value being greater than the helium content threshold, detecting that the heat transfer tube of the high-temperature gas-cooled reactor steam generator is leaking, and using the detection result of the leakage of the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the second detection result.

[0015] In some embodiments of the present application, the final determination of the integrity of the high-temperature gas-cooled reactor steam generator heat transfer tube based on the first detection result and the second detection result includes: in response to at least one of the first detection result and the second detection result indicating that the high-temperature gas-cooled reactor steam generator heat transfer tube has a leak, the final determination that the high-temperature gas-cooled reactor steam generator heat transfer tube has a leak.

[0016] A second embodiment of the present application provides a system for detecting the integrity of heat transfer tubes of a high-temperature gas-cooled reactor steam generator, comprising:

[0017] a sampling module, configured to sample the helium in the primary circuit of the nuclear power plant in response to the nuclear power plant operating state being a reactor power operation mode, to obtain a first helium sample and a second helium sample;

[0018] a detection module, configured to detect a humidity value of the first helium sample and an impurity content of the second helium sample;

[0019] a first acquisition module, configured to obtain a first detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator according to the humidity value of the first helium sample and the impurity content of the second helium sample;

[0020] a second acquisition module configured to, in response to the nuclear power plant operating state being a shutdown overhaul mode, perform a helium leak test on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator;

[0021] A determination module is used to finally determine the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator based on the first detection result and the second detection result.

[0022] In some embodiments of the present application, the sampling module is specifically used to: sample the helium in the primary circuit of the nuclear power plant at the outlet of the helium blower in the primary circuit of the nuclear power plant to obtain the first helium sample.

[0023] In some embodiments of the present application, the detection module is specifically used to: send the first helium sample to the humidity measuring device through a sampling pipe for measurement to obtain the humidity value of the first helium sample; after the humidity measuring device completes the measurement, return the first helium sample to the helium blower inlet of the primary circuit to utilize the pressure difference between the helium blower outlet and the helium blower inlet to keep the gas in the humidity measuring device circulating.

[0024] In some embodiments of the present application, the first acquisition module is specifically configured to: compare the humidity value of the first helium sample with a preset humidity threshold; compare the impurity content of the second helium sample with a preset impurity content threshold; in response to the humidity value of the first helium sample being greater than the humidity threshold and / or the impurity content of the second helium sample being greater than the impurity content threshold, detect the presence of a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, and use the detection result of the leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the first detection result.

[0025] In some embodiments of the present application, the second acquisition module is specifically used to: evacuate the secondary side of the high-temperature gas-cooled reactor steam generator and inflate and pressurize the primary side of the high-temperature gas-cooled reactor steam generator with helium; detect the helium content on the secondary side of the high-temperature gas-cooled reactor steam generator with a helium mass spectrometer to obtain a helium content value; compare the helium content value with a preset helium content threshold; in response to the helium content value being greater than the helium content threshold, detect the presence of a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, and use the detection result of the leakage in the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the second detection result.

[0026] In some embodiments of the present application, the determination module is specifically used to: in response to at least one of the first detection result and the second detection result indicating that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, ultimately determine that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator.

[0027] According to the method for detecting the integrity of the heat transfer tubes of a high-temperature gas-cooled reactor steam generator according to an embodiment of the present application, when the nuclear power plant is operating in the reactor power operation mode, the helium humidity and impurity content in the primary circuit of the nuclear power plant are detected online. When the nuclear power plant is operating in the shutdown overhaul mode, the heat transfer tubes of the high-temperature gas-cooled reactor steam generator are tested for helium leaks. This method combines online testing and non-destructive testing of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator to comprehensively assess the integrity of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator, thereby promptly detecting leaks in the heat transfer tubes, improving the accuracy of the integrity testing of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator steam generators, and ensuring the safe operation of the unit.

[0028] Additional aspects and advantages of the present application will be given in part in the description below, and in part will become apparent from the description below, or will be learned through practice of the present application. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] The above and / or additional aspects and advantages of the present application will become apparent and easily understood from the following description of the embodiments in conjunction with the accompanying drawings, in which:

[0030] Figure 1 A schematic flow chart of a method for detecting the integrity of a heat transfer tube of a high-temperature gas-cooled reactor steam generator provided in an embodiment of the present application;

[0031] Figure 2 A schematic flow chart of another method for detecting the integrity of heat transfer tubes of a high-temperature gas-cooled reactor steam generator provided in an embodiment of the present application;

[0032] Figure 3 A schematic diagram of a system for detecting the integrity of heat transfer tubes in a high-temperature gas-cooled reactor steam generator provided in an embodiment of the present application. DETAILED DESCRIPTION

[0033] The following describes in detail embodiments of the present application, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are intended to be used to explain the present application, and should not be construed as limiting the present application.

[0034] The present application provides a method and system for detecting the integrity of heat transfer tubes in a high-temperature gas-cooled reactor steam generator. Specifically, the following describes the method and system for detecting the integrity of heat transfer tubes in a high-temperature gas-cooled reactor steam generator according to an embodiment of the present application with reference to the accompanying drawings.

[0035] Figure 1 This is a flow chart of a method for detecting the integrity of a heat transfer tube of a high temperature gas-cooled reactor steam generator provided in an embodiment of the present application. Figure 1 As shown, the method for detecting the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator includes the following steps:

[0036] Step 101 : In response to a nuclear power plant operating state being a reactor power operation mode, helium in a primary circuit of the nuclear power plant is sampled to obtain a first helium sample and a second helium sample.

[0037] Step 102 : Detecting the humidity value of the first helium sample and the impurity content of the second helium sample.

[0038] In some embodiments of the present application, the impurity content of the second helium sample may include but is not limited to H 2 O content.

[0039] Step 103 : Obtain a first detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator according to the humidity value of the first helium sample and the impurity content of the second helium sample.

[0040] As an example, the humidity value of the first helium sample can be compared with a preset humidity threshold. If the humidity value of the first helium sample is greater than the humidity threshold, a leak in the heat transfer pipe of the high-temperature gas-cooled reactor steam generator is detected, and the leak detection result of the heat transfer pipe of the high-temperature gas-cooled reactor steam generator is used as the first detection result.

[0041] As another example, the impurity content of the second helium sample can be compared with a preset impurity content threshold. If the impurity content of the second helium sample is greater than the impurity content threshold, a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator is detected, and the leak detection result of the heat transfer tube of the high-temperature gas-cooled reactor steam generator is used as the first detection result.

[0042] As another example, the humidity value of the first helium sample can be compared with a preset humidity threshold, and the impurity content of the second helium sample can be compared with a preset impurity content threshold. If the humidity value of the first helium sample is greater than the humidity threshold, and the impurity content of the second helium sample is greater than the impurity content threshold, a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator is detected, and the detection result of the leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator is used as the first detection result.

[0043] Step 104 , in response to the nuclear power plant operating state being in the shutdown overhaul mode, performing helium leak detection on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator.

[0044] In an embodiment of the present application, when a nuclear power plant is operating in a shutdown overhaul mode, the secondary side of the high-temperature gas-cooled reactor steam generator can be evacuated, and the primary side of the high-temperature gas-cooled reactor steam generator can be inflated and pressurized with helium. The helium content of the secondary side of the high-temperature gas-cooled reactor steam generator is detected using a helium mass spectrometer to obtain a helium content value, which is then compared with a preset helium content threshold. If the helium content value is greater than the preset helium content threshold, a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator is detected, and the leak detection result of the heat transfer tube of the high-temperature gas-cooled reactor steam generator is used as a second detection result.

[0045] Step 105 : Based on the first test result and the second test result, the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator is finally determined.

[0046] In an embodiment of the present application, if at least one of the first detection result and the second detection result indicates that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, it can be finally determined that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, and the operating personnel can be reminded to pay attention to the leakage of the steam generator heat transfer tube through alarms or other means, so that certain measures can be taken in a timely manner to deal with it.

[0047] According to the method for detecting the integrity of the heat transfer tubes of a high-temperature gas-cooled reactor steam generator according to an embodiment of the present application, when the nuclear power plant is operating in the reactor power operation mode, the helium humidity and impurity content in the primary circuit of the nuclear power plant are detected online. When the nuclear power plant is operating in the shutdown overhaul mode, the heat transfer tubes of the high-temperature gas-cooled reactor steam generator are tested for helium leaks. This method combines online testing and non-destructive testing of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator to comprehensively assess the integrity of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator, thereby promptly detecting leaks in the heat transfer tubes, improving the accuracy of the integrity testing of the heat transfer tubes of the high-temperature gas-cooled reactor steam generator steam generators, and ensuring the safe operation of the unit.

[0048] Figure 2 This is a flow chart of another method for detecting the integrity of a heat transfer tube of a high temperature gas-cooled reactor steam generator provided in an embodiment of the present application. Figure 2 As shown, the method for detecting the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator includes the following steps:

[0049] Step 201 : In response to the nuclear power plant operating state being a reactor power operation mode, helium in a primary circuit of the nuclear power plant is sampled to obtain a first helium sample and a second helium sample.

[0050] Optionally, in some embodiments of the present application, the helium in the primary circuit of the power plant may be sampled once every 72 hours to obtain a first helium sample and a second helium sample.

[0051] Step 202: Send the first helium sample through a sampling pipe to a humidity measuring device for measurement to obtain a humidity value of the first helium sample.

[0052] As one possible implementation, helium gas in the primary circuit of a nuclear power plant can be sampled at the outlet of the helium blower in the primary circuit to obtain a first helium sample. As an example, the humidity measurement device can be a Class 1E humidity measurement device. It should be noted that after the humidity measurement device completes the measurement, the first helium sample is returned to the inlet of the helium blower in the primary circuit. This allows the pressure differential between the helium blower outlet and the inlet to maintain gas circulation in the humidity measurement device.

[0053] Step 203: Detect the impurity content of the second helium sample.

[0054] Step 204 : Obtain a first detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator based on the humidity value of the first helium sample and the impurity content of the second helium sample.

[0055] Step 205 , in response to the nuclear power plant operating state being in the shutdown overhaul mode, performing helium leak detection on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator.

[0056] Step 206 : In response to at least one of the first detection result and the second detection result indicating that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking, it is finally determined that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking.

[0057] Optionally, in some embodiments of the present application, if the first detection result indicates a leak in a HTGR steam generator heat transfer tube, the leak is addressed, including but not limited to locating the cause, shortening the sampling interval, restoring the primary circuit humidity value, and shutting down the unit. If the second detection result indicates a leak in a HTGR steam generator heat transfer tube, a helium leak test may be performed on each steam generator heat transfer tube to locate the leaking tube. Once the leaking tube is located, the tube may be plugged.

[0058] According to the method for detecting the integrity of heat transfer tubes in a high-temperature gas-cooled reactor steam generator (HTGR) according to an embodiment of the present application, when the nuclear power plant is operating in reactor power mode, a first helium sample is collected through a humidity measuring device, and the humidity value of the first helium sample is measured. After the humidity measuring device completes the measurement, the first helium sample is returned to the helium blower inlet of the primary circuit, so that the pressure differential between the helium blower outlet and the helium blower inlet maintains the gas circulation of the humidity measuring device. This method provides real-time detection of the helium humidity and impurity content in the primary circuit of the nuclear power plant. When the nuclear power plant is operating in shutdown and overhaul mode, helium leak detection is performed on the HTGR steam generator heat transfer tubes. This method combines online testing and nondestructive testing of the steam generator heat transfer tubes to comprehensively assess the integrity of the HTGR steam generator heat transfer tubes, enabling timely detection of heat transfer tube leaks, improving the accuracy of integrity testing of the HTGR steam generator heat transfer tubes, and providing appropriate treatment for different leak situations to ensure safe operation of the unit.

[0059] Figure 3 This is a schematic diagram of a detection system for the integrity of a heat transfer tube of a high temperature gas-cooled reactor steam generator provided in an embodiment of the present application. Figure 3 As shown, the detection system for the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator provided in the embodiment of the present application includes: a sampling module 301, a detection module 302, a first acquisition module 303, a second acquisition module 304 and a determination module 305.

[0060] The sampling module 301 is configured to sample the helium in the primary circuit of the nuclear power plant in response to the nuclear power plant operating condition being the reactor power operation mode, to obtain a first helium sample and a second helium sample.

[0061] In some embodiments of the present application, the sampling module 301 is specifically used to: sample the helium in the primary circuit of the nuclear power plant at the outlet of the helium blower in the primary circuit of the nuclear power plant to obtain a first helium sample.

[0062] The detection module 302 is configured to detect the humidity value of the first helium sample and the impurity content of the second helium sample.

[0063] In some embodiments of the present application, the detection module 302 is specifically configured to: deliver the first helium sample through a sampling pipe to a humidity measurement device for measurement to obtain a humidity value of the first helium sample. After the humidity measurement device completes the measurement, the first helium sample is returned to the inlet of the helium blower of the primary circuit, thereby utilizing the pressure difference between the helium blower outlet and the helium blower inlet to maintain gas circulation in the humidity measurement device.

[0064] The first acquisition module 303 is configured to obtain a first detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator according to the humidity value of the first helium sample and the impurity content of the second helium sample.

[0065] In some embodiments of the present application, the first acquisition module 303 is specifically configured to: compare the humidity value of the first helium sample with a preset humidity threshold; compare the impurity content of the second helium sample with a preset impurity content threshold; and, in response to the humidity value of the first helium sample being greater than the humidity threshold and / or the impurity content of the second helium sample being greater than the impurity content threshold, detect a leak in a heat transfer tube of a high-temperature gas-cooled reactor steam generator, and use the detection result of the leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the first detection result.

[0066] The second acquisition module 304 is configured to perform helium leak detection on the heat transfer tubes of the HTGR steam generator in response to the nuclear power plant operating state being in the shutdown overhaul mode, and obtain a second detection result of the integrity of the heat transfer tubes of the HTGR steam generator.

[0067] In some embodiments of the present application, the second acquisition module 304 is specifically configured to: evacuate the secondary side of the HTGR steam generator and inflate and pressurize the primary side of the HTGR steam generator with helium. Detect the helium content of the secondary side of the HTGR steam generator using a helium mass spectrometer to obtain a helium content value. Compare the helium content value with a preset helium content threshold. In response to the helium content value being greater than the helium content threshold, detect a leak in the HTGR steam generator heat transfer tube, and use the leak detection result as the second detection result.

[0068] The determination module 305 is configured to ultimately determine the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator based on the first detection result and the second detection result.

[0069] In some embodiments of the present application, the determination module 305 is specifically used to: in response to at least one of the first detection result and the second detection result indicating that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, ultimately determine that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator.

[0070] Regarding the system in the above embodiment, the specific manner in which each module performs operations has been described in detail in the embodiment of the method, and will not be elaborated here.

[0071] According to the HTGR steam generator heat transfer tube integrity detection system of the embodiment of the present application, when the nuclear power plant is operating in the reactor power operation mode, the helium humidity and impurity content in the nuclear power plant's primary circuit are detected online. When the nuclear power plant is operating in the shutdown overhaul mode, the HTGR steam generator heat transfer tubes are tested for helium leaks. This combines online testing and non-destructive testing of the steam generator heat transfer tubes to comprehensively assess the integrity of the HTGR steam generator heat transfer tubes, enabling timely detection of heat transfer tube leaks, improving the accuracy of HTGR steam generator heat transfer tube integrity testing, and ensuring safe operation of the unit.

[0072] In the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art can combine and combine different embodiments or examples described in this specification and features of different embodiments or examples without contradiction.

[0073] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of the technical features being referred to. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of such features. Throughout the description of this application, "plurality" means at least two, for example, two, three, etc., unless otherwise specifically defined.

[0074] Any process or method description in a flowchart or otherwise described herein may be understood to represent a module, segment or portion of code comprising one or more executable instructions for implementing the steps of a custom logical function or process, and the scope of the preferred embodiments of the present application includes alternative implementations in which functions may be performed out of the order shown or discussed, including performing functions in a substantially simultaneous manner or in the reverse order depending on the functions involved, which should be understood by those skilled in the art to which the embodiments of the present application belong.

[0075] It is understandable that the above embodiments are exemplary and should not be construed as limiting the present application. A person skilled in the art may change, modify, replace and modify the above embodiments within the scope of the present application.

Claims

1. A method for detecting the integrity of heat transfer tubes of a high-temperature gas-cooled reactor steam generator, characterized in that: The following steps are involved: In response to the nuclear power plant operating state being a reactor power operation mode, sampling helium in a primary circuit of the nuclear power plant to obtain a first helium sample and a second helium sample; detecting the humidity value of the first helium sample and the impurity content of the second helium sample; comprising: delivering the first helium sample to a humidity measuring device through a sampling pipe for measurement to obtain the humidity value of the first helium sample; and returning the first helium sample to the inlet of the helium blower of the primary circuit after the humidity measuring device completes the measurement, so as to maintain the gas circulation of the humidity measuring device by utilizing the pressure difference between the outlet of the helium blower and the inlet of the helium blower; Obtaining a first detection result of the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator based on the humidity value of the first helium sample and the impurity content of the second helium sample, comprising: comparing the humidity value of the first helium sample with a preset humidity threshold; comparing the impurity content of the second helium sample with a preset impurity content threshold; in response to the humidity value of the first helium sample being greater than the humidity threshold and / or the impurity content of the second helium sample being greater than the impurity content threshold, detecting that the heat transfer tube of the high-temperature gas-cooled reactor steam generator is leaking, and using the detection result of the leakage of the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the first detection result; In response to the nuclear power plant operating state being in a shutdown overhaul mode, performing a helium leak test on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second test result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator; Based on the first test result and the second test result, the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator is finally determined; when the first test result shows that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, the treatment methods adopted include finding the cause, shortening the sampling interval, restoring the humidity value of the first circuit, and deactivating the unit; when the second test result shows that there is a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, a helium leak test is performed on each heat transfer tube of the steam generator to find the location of the leaking heat transfer tube, and the tube is blocked after the location of the heat transfer tube is determined.

2. The method according to claim 1, characterized in that Sampling helium in the primary circuit of a nuclear power plant to obtain a first helium sample includes: The helium gas in the primary circuit of the nuclear power plant is sampled at an outlet of a helium blower in the primary circuit of the nuclear power plant to obtain the first helium gas sample.

3. The method according to claim 1, characterized in that The step of performing helium leak detection on the heat transfer tube of the high temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator includes: Evacuating the secondary side of the high-temperature gas-cooled reactor steam generator and inflating and pressurizing the primary side of the high-temperature gas-cooled reactor steam generator with helium; detecting the helium content on the secondary side of the high temperature gas-cooled reactor steam generator by a helium mass spectrometer to obtain a helium content value; comparing the helium content value with a preset helium content threshold; In response to the helium content value being greater than the helium content threshold, leakage is detected in the heat transfer tube of the high temperature gas-cooled reactor steam generator, and the detection result of leakage in the heat transfer tube of the high temperature gas-cooled reactor steam generator is used as the second detection result.

4. The method according to claim 1, wherein The step of finally determining the integrity of the heat transfer tube of the high temperature gas-cooled reactor steam generator based on the first test result and the second test result includes: In response to at least one of the first detection result and the second detection result indicating that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking, it is finally determined that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking.

5. A high-temperature gas-cooled reactor steam generator heat transfer tube integrity detection system, characterized in that: include: a sampling module, configured to sample the helium in the primary circuit of the nuclear power plant in response to the nuclear power plant operating state being a reactor power operation mode, to obtain a first helium sample and a second helium sample; a detection module, configured to detect the humidity value of the first helium sample and the impurity content of the second helium sample; specifically, configured to: deliver the first helium sample to a humidity measuring device through a sampling pipe for measurement to obtain the humidity value of the first helium sample; and after the humidity measuring device completes the measurement, return the first helium sample to the helium blower inlet of the primary circuit, so as to maintain gas circulation in the humidity measuring device by utilizing the pressure difference between the helium blower outlet and the helium blower inlet; a first acquisition module, configured to obtain a first detection result of the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator based on the humidity value of the first helium sample and the impurity content of the second helium sample; specifically configured to: compare the humidity value of the first helium sample with a preset humidity threshold; compare the impurity content of the second helium sample with a preset impurity content threshold; in response to the humidity value of the first helium sample being greater than the humidity threshold and / or the impurity content of the second helium sample being greater than the impurity content threshold, detect the presence of a leak in the heat transfer tube of the high-temperature gas-cooled reactor steam generator, and use the detection result of the leakage of the heat transfer tube of the high-temperature gas-cooled reactor steam generator as the first detection result; a second acquisition module configured to, in response to the nuclear power plant operating state being a shutdown overhaul mode, perform a helium leak test on the heat transfer tubes of the high temperature gas-cooled reactor steam generator to obtain a second detection result of the integrity of the heat transfer tubes of the high temperature gas-cooled reactor steam generator; A determination module is configured to ultimately determine the integrity of the heat transfer tube of the high-temperature gas-cooled reactor steam generator based on the first and second detection results; when the first detection result indicates that the heat transfer tube of the high-temperature gas-cooled reactor steam generator is leaking, the treatment methods adopted include finding the cause, shortening the sampling interval, restoring the primary circuit humidity value, and deactivating the unit; when the second detection result indicates that the heat transfer tube of the high-temperature gas-cooled reactor steam generator is leaking, performing a helium leak test on each heat transfer tube of the steam generator to locate the location of the leaking heat transfer tube, and performing pipe plugging after determining the location of the heat transfer tube.

6. The system according to claim 5, characterized in that The sampling module is specifically used for: The helium gas in the primary circuit of the nuclear power plant is sampled at an outlet of a helium blower in the primary circuit of the nuclear power plant to obtain the first helium gas sample.

7. The system according to claim 5, characterized in that The second acquisition module is specifically used for: Evacuating the secondary side of the high-temperature gas-cooled reactor steam generator and inflating and pressurizing the primary side of the high-temperature gas-cooled reactor steam generator with helium; detecting the helium content on the secondary side of the high temperature gas-cooled reactor steam generator by a helium mass spectrometer to obtain a helium content value; comparing the helium content value with a preset helium content threshold; In response to the helium content value being greater than the helium content threshold, leakage is detected in the heat transfer tube of the high temperature gas-cooled reactor steam generator, and the detection result of leakage in the heat transfer tube of the high temperature gas-cooled reactor steam generator is used as the second detection result.

8. The system according to claim 5, wherein: The determining module is specifically configured to: In response to at least one of the first detection result and the second detection result indicating that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking, it is finally determined that the heat transfer tube of the high temperature gas-cooled reactor steam generator is leaking.

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