Purification system effectiveness evaluation method and system based on nuclide analysis and medium

Abstract

The invention discloses a purification system effectiveness evaluation method and system based on nuclide analysis and a medium. Relates to the technical field of effectiveness evaluation. The method comprises the following steps: respectively acquiring radionuclide level data in water quality of a primary loop coolant of a reactor at the front end and the rear end of a reactor purification system, and preprocessing the radionuclide level data; inputting the preprocessed radionuclide level data into a constructed nuclide analysis model to calculate a nuclide evaluation factor; evaluating the effectiveness of the reactor purification system based on the nuclide evaluation factor; according to the scheme, the method is improved on the basis of an existing purification system effectiveness evaluation technology, through radionuclide analysis, based on the radionuclide level in reactor coolant water, the resin purification performance of the purification system is studied and judged, and the accuracy and the measurement efficiency are improved.

Description

Technical Field

[0001] The present invention relates to the technical field of effectiveness evaluation, and in particular to a purification system effectiveness evaluation method, system and medium based on nuclide analysis. Background Art

[0002] In the primary loop system of a nuclear power plant, a purification system is set up to remove soluble and insoluble impurities in the reactor coolant and ensure that the reactor coolant water quality indicators are within the specified limits. This system is the main water treatment material for the primary loop and its auxiliary systems of a pressurized water reactor nuclear power plant. It is used to purify fission products, corrosion products and impurity ions generated during operation to maintain the water quality of the primary loop system and reduce the radiation dose of the power plant. The purification system is usually equipped with two mixed bed purification ion exchangers and one cationic bed purification ion exchanger. After a long period of continuous operation under high temperature and high pressure water conditions, the purification capacity of this series will be reduced. Once the ion exchanger function in the purification system fails, the radioactive nuclides in the primary loop coolant will exceed the standard.

[0003] At present, nuclear power plants at home and abroad mainly determine the effectiveness of purification systems by monitoring characteristic parameters, such as changes in conductivity before and after purification, cumulative time, cumulative flow value, or typical ion content after purification (such as chloride ions, fluoride ions, etc.). However, the measurement accuracy of this invention is low and the measurement time is long. Summary of the invention

[0004] The technical problem to be solved by the present invention is: currently, nuclear power plants mainly determine the effectiveness of purification systems by monitoring characteristic parameters, such as conductivity changes before and after purification, cumulative time, cumulative flow values ​​or typical ion contents after purification (such as chloride ions, fluorine ions, etc.), but this method has low measurement accuracy and a long measurement time; the purpose of the present invention is to provide a purification system effectiveness evaluation method, system and medium based on radionuclide analysis, through radionuclide analysis, based on the radionuclide level in the reactor coolant water quality, to judge the purification performance of the purification system resin, and improve accuracy and measurement efficiency.

[0005] The present invention is achieved through the following technical solutions:

[0006] This program provides a purification system effectiveness evaluation method based on radionuclide analysis, including:

[0007] At the front end and the back end of the reactor purification system, respectively collect the radionuclide level data in the reactor primary loop coolant water quality, and pre-process the radionuclide level data;

[0008] Input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor;

[0009] The effectiveness of the reactor purification system is evaluated based on nuclide assessment factors.

[0010] Working principle of this scheme: At present, nuclear power plants mainly determine the effectiveness of purification systems by monitoring characteristic parameters, such as conductivity changes before and after purification, cumulative time, cumulative flow value or typical ion content after purification (such as chloride ions, fluoride ions, etc.), but this method has low measurement accuracy and long measurement time; the purpose of the present invention is to provide a purification system effectiveness evaluation method, system and medium based on radionuclide analysis, through radionuclide analysis, based on the radionuclide level in the reactor coolant water quality, to determine the purification performance of the purification system resin, improve accuracy and measurement efficiency.

[0011] Compared with the traditional evaluation method of judging the effectiveness of resin by conductivity change or typical ion content after purification (such as chloride ions, fluoride ions, etc.), the resin status is reflected by the chemical properties of the primary water loop, and the effectiveness of the resin is not directly fed back from the functional characteristics actually performed by the resin. In addition, the cumulative time and cumulative flow value methods are easily affected by uncertain factors in the environment, and the actual working conditions are not taken into account, and the state of the resin cannot be directly reflected. This method is based on the adsorption function of the resin on primary radioactive substances. It compares and analyzes the radioactivity levels of typical nuclides in the primary water loop before and after resin adsorption, quantitatively calculates the radioactivity change ratio, and directly judges the state of the resin.

[0012] In addition, for some special reactors, the components in the first-loop coolant water cannot undergo replacement reactions with traditional typical ions, so traditional ion content monitoring methods are difficult to apply. This scheme is based on the level of radioactive nuclides in the reactor coolant water quality, avoiding chemical reactions of the reactor coolant water quality. Instead, the nuclide assessment factor is calculated through the nuclide analysis model, and the assessment is performed based on the nuclide assessment factor. This scheme can be applied to scenarios where traditional ion content monitoring methods are difficult to apply, thus expanding the application scenarios.

[0013] A further optimized solution is that the radioactive nuclides include: Na-24, Mo-99, I-133, I-135 and Cs-138.

[0014] A further optimization scheme is that the radionuclide level data includes: the specific activity of each radionuclide at the front end of the reactor purification system; the specific activity of each radionuclide at the front end of the reactor purification system.

[0015] A further optimization scheme is that the preprocessing includes methods: smoothing, peak finding, peak stripping and activity calculation of radionuclide level data.

[0016] A further optimization scheme is that the nuclide analysis model includes:

[0017]

[0018]

[0019] Where ε represents the total nuclide change assessment factor; η represents the single nuclide change assessment factor; A i ′ represents the specific activity of radionuclide i at the front end of the reactor purification system; A i It represents the specific activity of radionuclide i at the back end of the reactor purification system; i = 1, 2, …, n; n is the total number of radionuclides.

[0020] A further optimization scheme is that the effectiveness evaluation of the reactor purification system based on the nuclide evaluation factor includes the following methods:

[0021] A first threshold interval of the total nuclide change assessment factor is set, and when the total nuclide change assessment factor is less than the first threshold interval, the reactor purification system is judged to be ineffective; when the total nuclide change assessment factor is greater than the first threshold interval, the reactor purification system is judged to be effective;

[0022] When the total nuclide change assessment factor is within the first threshold interval, the effectiveness of the reactor purification system is determined by a single nuclide change assessment factor.

[0023] A further optimization scheme is that the effectiveness of the reactor purification system is determined by using a single nuclide change assessment factor, including the following method:

[0024] A second threshold is set to determine the size of the single nuclide change assessment factor and the second threshold, and the number n of single nuclide change assessment factors whose single nuclide change assessment factors are greater than the second threshold is counted. If n ≥ 1, the reactor purification system is effective; if all single nuclide change assessment factors are ≤ the second threshold, the reactor purification system fails.

[0025] A further optimization scheme is that the method for determining the first threshold interval and the second threshold includes:

[0026] Combining the radioactivity adsorption capacity of the resin, analyzing the conductivity of the resin before and after failure, the typical ion content after purification (such as chloride ions, fluoride ions, etc.), and the difference in radioactivity levels, after multiple fittings, the first threshold interval was (2,5], and the second threshold was 5.

[0027] The present solution also provides a reactor purification system effectiveness evaluation system based on nuclide analysis, which is used to implement the above-mentioned reactor purification system effectiveness evaluation method based on nuclide analysis. The system includes:

[0028] A collection module, used for collecting radionuclide level data in the coolant water quality of the reactor primary loop at the front end and the back end of the reactor purification system respectively;

[0029] A preprocessing module, used for preprocessing the radionuclide level data;

[0030] A calculation module is used to input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor;

[0031] An evaluation module is used to evaluate the effectiveness of the reactor purification system based on nuclide assessment factors.

[0032] The present solution also provides a computer-readable medium having a computer program stored thereon, and the computer program is executed by a processor to implement the above-mentioned method for evaluating the effectiveness of a reactor purification system based on nuclide analysis.

[0033] Compared with the prior art, the present invention has the following advantages and beneficial effects:

[0034] The present invention provides a purification system effectiveness evaluation method, system and medium based on radionuclide analysis. This scheme improves the method on the basis of the existing purification system effectiveness evaluation technology, and through radionuclide analysis, based on the radionuclide level in the reactor coolant water quality, the purification performance of the purification system resin is determined to improve the accuracy and measurement efficiency.

[0035] Compared with the traditional evaluation method of judging the effectiveness of resin by conductivity change or typical ion content after purification (such as chloride ions, fluoride ions, etc.), the resin status is reflected by the chemical properties of the primary water loop, and the effectiveness of the resin is not directly fed back from the functional characteristics actually performed by the resin. In addition, the cumulative time and cumulative flow value methods are easily affected by uncertain factors in the environment, and the actual working conditions are not taken into account, and the state of the resin cannot be directly reflected. This method is based on the adsorption function of the resin on primary radioactive substances. It compares and analyzes the radioactivity levels of typical nuclides in the primary water loop before and after resin adsorption, quantitatively calculates the radioactivity change ratio, and directly judges the state of the resin.

[0036] The present invention provides a purification system effectiveness assessment method, system and medium based on nuclide analysis. This scheme is based on the level of radioactive nuclides in the reactor coolant water quality, avoids chemical reactions in the reactor coolant water quality, and instead calculates the nuclide assessment factor in the nuclide analysis model. The assessment is performed based on the nuclide assessment factor, which can be applicable to scenarios where traditional ion content monitoring methods are difficult to apply, thereby expanding the application scenarios. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the following briefly introduces the drawings required for use in the embodiments. It should be understood that the following drawings only illustrate certain embodiments of the present invention and should not be regarded as limiting the scope. For those of ordinary skill in the art, other relevant drawings can be obtained based on these drawings without creative work. In the drawings:

[0038] Figure 1 The schematic diagram of the process of evaluating the effectiveness of the reactor purification system based on nuclide analysis is shown in FIG.

[0039] Figure 2 This is a schematic diagram of the effectiveness evaluation system for the reactor purification system based on nuclide analysis;

[0040] Figure 3 It is a schematic diagram of the flow of the primary coolant transmission to the resin failure monitoring and analysis device;

[0041] Figure 4 This is a schematic diagram of the software interface for the transmission of a loop coolant to the resin failure monitoring and analysis device. DETAILED DESCRIPTION

[0042] In order to make the objectives, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with embodiments and drawings. The exemplary embodiments of the present invention and their description are only used to explain the present invention and are not intended to limit the present invention.

[0043] At present, nuclear power plants at home and abroad mainly determine the effectiveness of purification systems by monitoring characteristic parameters, such as changes in conductivity before and after purification, cumulative time, cumulative flow value, or typical ion content after purification (such as chloride ions, fluoride ions, etc.). However, the measurement accuracy of this invention is low and the measurement time is long.

[0044] In order to solve the above technical problems, this solution provides the following embodiments:

[0045] Example 1

[0046] This embodiment provides a method for evaluating the effectiveness of a reactor purification system based on nuclide analysis. The method mainly characterizes the effectiveness of the entire reactor purification system by whether the resin in the reactor purification system is ineffective. Figure 1 As shown, including:

[0047] Step 1: collecting radionuclide level data in the coolant water quality of the reactor primary loop at the front end and the back end of the reactor purification system, respectively, and preprocessing the radionuclide level data;

[0048] The radionuclide level data include: the specific activity of each radionuclide at the front end of the reactor purification system; the specific activity of each radionuclide at the front end of the reactor purification system.

[0049] During the specific implementation process, this embodiment adds resin monitoring sampling loops at the front end and the back end of the purification system, transmits the first-loop coolant at the front end and the back end of the purification system to the resin failure monitoring and analysis device, and uses the radionuclide analysis method to judge the resin purification performance based on the radionuclide level in the reactor coolant water quality.

[0050] The nuclear reactor corresponding to this embodiment has the following radioactive nuclides: Na-24, Mo-99, I-133, I-135 and Cs-138. These nuclides are typical long-life nuclides in the primary coolant;

[0051] The preprocessing includes methods: smoothing, peak finding, peak stripping and activity calculation of radionuclide level data.

[0052] Step 2: Input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor;

[0053] The nuclide analysis model includes:

[0054]

[0055] Where ε represents the total nuclide change assessment factor; η represents the single nuclide change assessment factor; A i ′ represents the specific activity of radionuclide i at the front end of the reactor purification system; A i represents the specific activity of radionuclide i at the rear end of the reactor purification system; i = 1, 2, ..., n; n is the total number of radionuclides. The specific application calculation process of this embodiment is:

[0056]

[0057] Where A′ Na-24 , A′ Mo-99 , A I ' -133 , A I ' -135 , A′ Cs-138 are the specific activities of radionuclides Na-24, Mo-99, I-133, I-135 and Cs-138 before purification, A Na-24 , A Mo-99 , A I-133 , A I-135 , A Cs-138 They are the specific activities of the radionuclides Na-24, Mo-99, I-133, I-135 and Cs-138 after purification.

[0058] Step 3: Evaluate the effectiveness of the reactor purification system based on the nuclide assessment factors.

[0059] The effectiveness assessment of the reactor purification system based on the nuclide assessment factor includes the following methods:

[0060] A first threshold interval of the total nuclide change assessment factor is set, and when the total nuclide change assessment factor is less than the first threshold interval, the reactor purification system is judged to be ineffective; when the total nuclide change assessment factor is greater than the first threshold interval, the reactor purification system is judged to be effective;

[0061] When the total nuclide change assessment factor is within the first threshold interval, the effectiveness of the reactor purification system is determined by a single nuclide change assessment factor.

[0062] The method of determining the effectiveness of a reactor purification system by using a single nuclide change assessment factor includes:

[0063] A second threshold is set to determine the size of the single nuclide change assessment factor and the second threshold, and the number n of single nuclide change assessment factors whose single nuclide change assessment factors are greater than the second threshold is counted. If n ≥ 1, the reactor purification system is effective; if all single nuclide change assessment factors are ≤ the second threshold, the reactor purification system fails.

[0064] The method for determining the first threshold interval and the second threshold includes:

[0065] Combining the radioactivity adsorption capacity of the resin, analyzing the conductivity of the resin before and after failure, the typical ion content after purification (such as chloride ions, fluoride ions, etc.), and the difference in radioactivity levels, after multiple fittings, the first threshold interval was (2,5], and the second threshold was 5.

[0066] In the specific implementation process, the first threshold interval obtained according to the above method is (2, 5); the second threshold is 5;

[0067] If ε>5, the effectiveness of the purification system meets the requirements;

[0068] If 5≥ε>2, and at least one η>5, the effectiveness of the purification system meets the requirements;

[0069] If 5≥ε>2, and all η≤5, the effectiveness of the purification system is lost and the resin needs to be replaced;

[0070] If ε≤2, the effectiveness of the purification system is lost and the resin needs to be replaced.

[0071] The purpose of the present invention is to provide a purification system effectiveness evaluation method, system and medium based on radionuclide analysis, through radionuclide analysis, based on the radionuclide level in the reactor coolant water quality, the total specific activity ratio of the nuclides before and after purification, and the specific activity ratio of each main nuclide; to judge the purification performance of the purification system resin, improve accuracy and measurement efficiency.

[0072] In addition, for some special reactors, the components in the first-loop coolant water cannot undergo replacement reactions with traditional typical ions, so traditional ion content monitoring methods are difficult to apply. This scheme is based on the level of radioactive nuclides in the reactor coolant water quality, avoiding chemical reactions of the reactor coolant water quality. Instead, the nuclide assessment factor is calculated through the nuclide analysis model, and the assessment is performed based on the nuclide assessment factor. This scheme can be applied to scenarios where traditional ion content monitoring methods are difficult to apply, thus expanding the application scenarios.

[0073] Example 2

[0074] The reactor purification system effectiveness evaluation system based on nuclide analysis in this embodiment is used to implement the reactor purification system effectiveness evaluation method based on nuclide analysis described in Example 1, such as Figure 2 As shown, the system comprises:

[0075] A collection module, used for collecting radionuclide level data in the coolant water quality of the reactor primary loop at the front end and the back end of the reactor purification system respectively;

[0076] A preprocessing module, used for preprocessing the radionuclide level data;

[0077] A calculation module is used to input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor;

[0078] An evaluation module is used to evaluate the effectiveness of the reactor purification system based on nuclide assessment factors.

[0079] like Figure 3 and Figure 4 As shown, the reactor purification system effectiveness evaluation system based on nuclide analysis provided in this embodiment is mainly composed of a high-purity germanium detector, a multi-channel analyzer, an energy spectrum analysis software, a resin failure analysis software, a flow meter, a pressure gauge, a valve, etc., and is used to transmit the coolant of the first-loop at the front end and the back end of the purification system to the resin failure monitoring and analysis device, and through the invention of radionuclide analysis, the resin purification performance is judged based on the radionuclide level in the reactor coolant water quality.

[0080] After testing, the specific activity A' of each nuclide before purification Na-24 , A′ Mo-99 , AI ' -133 , A I ' -135 , A′ Cs-138 5.0×10 7 Bq / m 3 , 1.5×10 7 Bq / m 3 , 4.8×10 7 Bq / m 3 , 1.5×10 8 Bq / m 3 , 3.7×10 8 Bq / m 3 Specific activity A of each nuclide after purification Na-24 , A Mo-99 , A I-133 , A I-135 , A Cs-138 4.5×10 7 Bq / m 3 , 1.2×10 7 Bq / m 3 , 4.6×10 7 Bq / m 3 , 1.2×10 8 Bq / m 3 , 3.5×10 8 Bq / m 3 , we calculated ε = 1.10, η Na-24 , η Mo-99 , η I-133 , η I-135 , η Cs-138 If they are 1.11, 4.00, 1.25 and 1.05 respectively, it is judged that the purification system has lost its effectiveness and the resin needs to be replaced.

[0081] Example 3

[0082] This embodiment provides a computer-readable medium having a computer program stored thereon, and the computer program is executed by a processor to implement the method for evaluating the effectiveness of a reactor purification system based on nuclide analysis as described in Embodiment 2; specifically, the following steps are performed:

[0083] Step 1: collecting radionuclide level data in the coolant water quality of the reactor primary loop at the front end and the back end of the reactor purification system, respectively, and preprocessing the radionuclide level data;

[0084] Step 2: Input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor;

[0085] Step 3: Evaluate the effectiveness of the reactor purification system based on the nuclide assessment factors.

[0086] The software system corresponding to this embodiment is as follows Figure 4 As shown, the software interface of the first-loop coolant transmission to the resin failure monitoring and analysis device.

[0087] This solution transmits the primary coolant at the front and back ends of the purification system to the resin failure monitoring and analysis device. Through the radionuclide analysis method, the resin purification performance is judged based on the radionuclide level in the reactor coolant water quality, thereby improving the accuracy and efficiency of the effectiveness analysis of the reactor purification system.

[0088] The specific implementation methods described above further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above description is only a specific implementation method of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A purification system effectiveness evaluation method based on radionuclide analysis, characterized in that: include: At the front end and the back end of the reactor purification system, respectively collect the radionuclide level data in the reactor primary loop coolant water quality, and pre-process the radionuclide level data; Input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor; The effectiveness of the reactor purification system is evaluated based on nuclide assessment factors.

2. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 1, characterized in that: The radionuclides include: Na-24, Mo-99, I-133, I-135 and Cs-138.

3. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 1, characterized in that: The radionuclide level data include: the specific activity of each radionuclide at the front end of the reactor purification system; the specific activity of each radionuclide at the front end of the reactor purification system.

4. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 1, characterized in that: The preprocessing includes methods: smoothing, peak finding, peak stripping and activity calculation of radionuclide level data.

5. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 3, characterized in that: The nuclide analysis model includes: Where ε represents the total nuclide change assessment factor; η represents the single nuclide change assessment factor; A i ′ represents the specific activity of radionuclide i at the front end of the reactor purification system; A i It represents the specific activity of radionuclide i at the back end of the reactor purification system; i = 1, 2, …, n; n is the total number of radionuclides.

6. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 5, characterized in that: The effectiveness evaluation of the reactor purification system based on the nuclide evaluation factor includes the following methods: A first threshold interval of the total nuclide change assessment factor is set, and when the total nuclide change assessment factor is less than the first threshold interval, the reactor purification system is judged to be ineffective; when the total nuclide change assessment factor is greater than the first threshold interval, the reactor purification system is judged to be effective; When the total nuclide change assessment factor is within the first threshold interval, the effectiveness of the reactor purification system is determined by a single nuclide change assessment factor.

7. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 1, characterized in that: The method of determining the effectiveness of a reactor purification system by using a single nuclide change assessment factor includes: A second threshold is set to determine the size of the single nuclide change assessment factor and the second threshold, and the number n of single nuclide change assessment factors whose single nuclide change assessment factors are greater than the second threshold is counted. If n ≥ 1, the reactor purification system is effective; if all single nuclide change assessment factors are ≤ the second threshold, the reactor purification system fails.

8. The method for evaluating the effectiveness of a purification system based on nuclide analysis according to claim 6, characterized in that: The method for determining the first threshold interval and the second threshold includes: Combining the radioactivity adsorption capacity of the resin, analyzing the conductivity of the resin before and after failure, the typical ion content after purification, and the difference in radioactivity level, after multiple fittings, the first threshold interval was (2,5], and the second threshold was 5.

9. A purification system effectiveness evaluation system based on radionuclide analysis, characterized in that: A purification system effectiveness evaluation method based on nuclide analysis for implementing any one of claims 1 to 8, the system comprising: A collection module, used for collecting radionuclide level data in the coolant water quality of the reactor primary loop at the front end and the back end of the reactor purification system respectively; A preprocessing module, used for preprocessing the radionuclide level data; A calculation module is used to input the pre-processed radionuclide level data into the constructed nuclide analysis model to calculate the nuclide assessment factor; An evaluation module is used to evaluate the effectiveness of the reactor purification system based on nuclide assessment factors.

10. A computer readable medium having a computer program stored thereon, characterized in that: The computer program is executed by a processor to implement the method for evaluating the effectiveness of a purification system based on nuclear analysis as described in any one of claims 1 to 8.

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