Comprehensive evaluation method and device for source item control of nuclear power plant, storage medium and electronic equipment

Abstract

The invention relates to a comprehensive evaluation method and device for source item control of a nuclear power plant, a storage medium and electronic equipment. The method comprises the following steps: acquiring multi-dimensional parameter data of each unit, and analyzing to generate a unit source item file; determining the score of the comprehensive evaluation index of the source item according to each evaluation dimension; calculating a radiation index of the overhaul area; weighting the radiation index of the overhaul area to obtain a radiation weighted value of the overhaul area; predicting the dose level of the overhaul collective dose based on the radiation weighted value of the overhaul area; analyzing based on the score of the comprehensive evaluation index of the source item and the dose level of the overhaul collective dose, and determining a corresponding relationship between the comprehensive evaluation index of the source item and / or the overhaul collective dose; dynamically maintaining a unit source item file according to the corresponding relation and providing a control strategy. According to the method, the influence on the overhaul collective dose can be evaluated, effective evaluation on the effect of the unit source item is realized, and a response strategy for source item control can be given in advance.

Description

Technical Field

[0001] The present invention relates to the technical field of evaluation of source term control in pressurized water reactors, and more specifically, to a comprehensive evaluation method, device, storage medium, and electronic device for source term control in nuclear power plants. Background Art

[0002] The unit source terms of nuclear power plants mainly include two categories: fission products and activation products. Optimizing the unit source term level, as a fundamental measure to control the radiation risk of the unit and reduce the collective dose, has always been an important part of the work of reducing the collective dose in each nuclear power plant.

[0003] Nuclear power plants face various practical problems in radiation source term control: the source term optimization measures that have been practiced show large differences in effects in different units (such as adding hydrogen peroxide multiple times, acid-base control, temperature control, etc.); the measures to fundamentally reduce the source term lack convincing prediction and evaluation capabilities (such as zinc injection, pH value optimization, fuel ultrasonic decontamination, etc.); the radiation index evaluation method based on a single dimension of dose rate cannot accurately explain the relationship between the primary loop source term, dose rate, and the radiation dose received by staff (such as a low index but a high dose, or a high index but a low dose).

[0004] Currently, the method used for source term effect evaluation is: by measuring the site dose rate at representative points, calculating the average value of each sub-region, and then averaging to obtain the regional index. This method is used to characterize the overall situation of the unit's radiation level, but when evaluating the impact on the overhaul collective dose, it has certain limitations due to the different working hours in each region. In addition, there are no good evaluation and control means for the overall level evaluation of the unit source term. Summary of the Invention

[0005] The technical problem to be solved by the present invention is to provide a comprehensive evaluation method, device, storage medium, and electronic device for source term control in nuclear power plants in view of the problems existing in the prior art.

[0006] The technical solution adopted by the present invention to solve its technical problems is to construct a comprehensive evaluation method for source term control in nuclear power plants, including the following steps:

[0007] Obtain parameter data of each unit in multiple dimensions, and generate a unit source term file based on the analysis and processing of the parameter data;

[0008] Obtain each evaluation dimension, and assign deduction / bonus points based on each evaluation dimension to obtain the score of the source term comprehensive evaluation index;

[0009] Statistically calculate according to the radiation indices of each sub-region of each unit to obtain the radiation index of the overhaul region;

[0010] Perform a weighted processing on the radiation index of the overhaul area to obtain the radiation weighted value of the overhaul area;

[0011] Predict the dose level of the overhaul collective dose based on the radiation weighted value of the overhaul area;

[0012] Analyze based on the score of the source term comprehensive evaluation index and the dose level of the overhaul collective dose to determine the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose;

[0013] Dynamically maintain the unit source term file according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose and provide a control strategy.

[0014] In the comprehensive evaluation method for nuclear power plant source term control according to the present invention, the parameter data of multiple dimensions of each unit includes: radiation index of the low-low water level area, manufacturer of the evaporator heat transfer tubes, fuel cycle length, number of fuel defects, unit purification duration, number of unit transients, and peak value of overhaul oxidation Co-60.

[0015] In the comprehensive evaluation method for nuclear power plant source term control according to the present invention, the obtaining of the parameter data of multiple dimensions of each unit and the generation of the unit source term file based on the parameter data analysis include:

[0016] Analyze and calculate the parameter data of the multiple dimensions respectively to determine the division intervals of each dimension;

[0017] Use the scoring method to assign values to the division intervals of each dimension to obtain the basic source term level of the unit;

[0018] Construct the unit source term file based on the basic source term level of the unit and the scores of the division areas of each dimension.

[0019] In the comprehensive evaluation method for nuclear power plant source term control according to the present invention, the unit source term file includes: single-unit source term file and / or multi-unit source term file.

[0020] In the comprehensive evaluation method for nuclear power plant source term control according to the present invention, each evaluation dimension includes: daily source term comprehensive evaluation dimension, non-refueling outage minor repair source term comprehensive evaluation dimension, overhaul source term comprehensive evaluation - unit control dimension, and good practice or measure comprehensive evaluation dimension.

[0021] In the comprehensive evaluation method for nuclear power plant source term control according to the present invention, the performing of the weighted processing on the radiation index of the overhaul area to obtain the radiation weighted value of the overhaul area includes:

[0022] Determine each sub-area of the overhaul area and obtain the radiation index of each sub-area;

[0023] Determine the man-hour weight of the radiation index for each sub-region;

[0024] Calculate according to the man-hour weight of the radiation index of each sub-region and the radiation index of each sub-region to obtain the radiation weighted value of the overhaul area.

[0025] In the comprehensive evaluation method for nuclear power plant source term control of the present invention, the daily source term comprehensive evaluation dimension, the non-refueling outage minor repair source term comprehensive evaluation dimension, and the overhaul source term comprehensive evaluation - unit control dimension are deduction dimensions, and the good practice or measure comprehensive evaluation dimension is an addition dimension. Moreover, the deduction proportion of the daily source term comprehensive evaluation dimension is 5%, the deduction proportion of the non-refueling outage minor repair source term comprehensive evaluation dimension is 10%, and the deduction proportion of the overhaul source term comprehensive evaluation - unit control dimension is 85%.

[0026] The present invention also provides a comprehensive evaluation device for nuclear power plant source term control, including:

[0027] A source term file construction unit, configured to obtain parameter data of each unit in multiple dimensions, and generate a unit source term file based on the analysis and processing of the parameter data;

[0028] A source comprehensive evaluation index tracking unit, configured to obtain each evaluation dimension, and perform deduction / addition assignment based on each evaluation dimension to obtain the score of the source term comprehensive evaluation index;

[0029] A regional radiation index determination unit, configured to perform statistical calculation according to the radiation index of each sub-region of each unit to obtain the radiation index of the overhaul area;

[0030] A weight correction unit, configured to perform weighted processing on the radiation index of the overhaul area to obtain the radiation weighted value of the overhaul area;

[0031] An overhaul collective dose assessment unit, configured to predict the dose level of the overhaul collective dose based on the radiation weighted value of the overhaul area;

[0032] An association relationship determination unit, configured to analyze based on the score of the source term comprehensive evaluation index and the dose level of the overhaul collective dose to determine the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose;

[0033] A dynamic maintenance and strategy output unit, configured to dynamically maintain the unit source term file and provide a control strategy according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose.

[0034] The present invention also provides a storage medium storing a computer program, which is adapted to be loaded by a processor to execute the steps of the comprehensive evaluation method for the source term control of a nuclear power plant as described above.

[0035] The present invention also provides an electronic device, including a memory and a processor. A computer program is stored in the memory, and the processor executes the steps of the comprehensive evaluation method for the source term control of a nuclear power plant as described above by calling the computer program stored in the memory.

[0036] Implementing the comprehensive evaluation method for the source term control of a nuclear power plant according to the present invention has the following beneficial effects: including: obtaining parameter data of each unit in multiple dimensions for analysis to generate a unit source term file; determining a source term comprehensive evaluation index according to the source term control data of each dimension, and performing deduction / bonus assignment based on the source term comprehensive evaluation index; calculating the radiation index of the overhaul area; performing weighted processing on the radiation index of the overhaul area to obtain a radiation weighted value of the overhaul area; calculating based on the radiation weighted value of the overhaul area to obtain a comprehensive value of the overhaul collective dose; analyzing based on the source term comprehensive evaluation index and the comprehensive value of the overhaul collective dose to determine the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose; dynamically maintaining the unit source term file according to the corresponding relationship and providing a control strategy. The present invention can not only evaluate the impact on the overhaul collective dose, effectively evaluate the effect of the unit source term, but also give a response strategy for source term control in advance. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] The present invention will be further described below in conjunction with the drawings and embodiments. In the drawings:

[0038] Figure 1 is a schematic flow chart of the comprehensive evaluation method for the source term control of a nuclear power plant provided by the present invention;

[0039] Figure 2 is a general functional logic diagram of the comprehensive evaluation method for the source term control of a nuclear power plant provided by the present invention;

[0040] Figure 3 is a logic diagram for constructing a unit source term file provided by the present invention;

[0041] Figure 4 is an evaluation logic diagram for the relationship between weight correction and overhaul collective dose provided by the present invention;

[0042] Figure 5 is a logic diagram for dynamically maintaining a unit source term file and providing a control strategy provided by the present invention;

[0043] Figure 6 is a functional block diagram of the comprehensive evaluation device for the source term control of a nuclear power plant provided by the present invention. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0044] The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are only a part of the embodiments of the present invention, rather than all the embodiments. All other embodiments obtained by those of ordinary skill in the art based on the embodiments of the present invention without creative efforts shall fall within the protection scope of the present invention.

[0045] To solve the problem that there are no good evaluation and control means for the source term in existing nuclear power plants, the present invention provides a comprehensive evaluation method for source term control in nuclear power plants. This method is for the evaluation and control of the unit source term, and is divided into an evaluation dimension, a reduction generation dimension, and an increase removal dimension. Among them, the reduction generation dimension and the increase removal dimension are both control means for source term control. By evaluating the current situation of the unit source term, technical means for reduction generation or increase removal are selected to optimize the current situation of the unit source term. After the technical implementation, the implementation effect is further evaluated, and the optimal technical measures are continuously selected according to the implementation effect to achieve the goal of continuously optimizing the unit source term, continuously achieving the optimal solution of source term control, and realizing the balance between input and output, cost and excellence.

[0046] Reference Figure 1 and Figure 2 , where Figure 1 is a flowchart of an embodiment of the comprehensive evaluation method for source term control in a nuclear power plant provided by the present invention, Figure 2 is a general functional logic diagram of the comprehensive evaluation method for source term control in a nuclear power plant provided by the present invention.

[0047] As Figure 1 shown, the comprehensive evaluation method for source term control in a nuclear power plant includes the following steps:

[0048] Step S101: Obtain parameter data of multiple dimensions of each unit, and generate a unit source term file based on the analysis and processing of the parameter data.

[0049] Optionally, in the embodiments of the present invention, the parameter data of multiple dimensions of each unit includes: radiation index in the low-low water level area, evaporator heat transfer tube manufacturer, fuel cycle length, number of fuel defects, unit purification duration, number of unit transients, and peak value of overhaul oxidation Co-60. Among them, the obtaining of the parameter data of multiple dimensions of each unit and the generation of a unit source term file based on the analysis and processing of the parameter data include: respectively analyzing and calculating the parameter data of multiple dimensions to determine the division intervals of each dimension; using a scoring method to assign values to the division intervals of each dimension to obtain the basic source term level of the unit; and constructing the unit source term file based on the basic source term level of the unit and the scores of the division regions of each dimension.

[0050] As Figure 3As shown, in the embodiments of the present invention, the generated unit source term file may include a single-unit source term file and / or a multi-unit source term file.

[0051] As Figure 3 shown, the radiation index in the very low water level area and the average value are divided into 5 interval dimensions, with scores: 20, 18, 16, 14, 12. The intervals are: [100, 150), [150, 200), [200, 250), [250, 300), [300, 350]. The manufacturers of the evaporator heat transfer tubes are divided into 2 interval dimensions. Among them, those produced by a specific manufacturer are 20 points, and those produced by other manufacturers are 5 points. The specific manufacturer is the manufacturer of the evaporator heat transfer tubes designated by the nuclear power plant. The fuel cycle length is divided into 5 interval dimensions according to the average value, and the scores are: 5, 4, 3, 2, 1 in sequence; the corresponding fuel cycle length intervals are: [1000, 1500), [1500, 2000), [2000, 2500), [2500, 3000), [3000, 3500]. The number of fuel defects can implement a point deduction system according to the number of fuel defects: that is, points are deducted according to the number of fuel breakages or neutron source breakages, 2 points are deducted each time. The unit purification duration is divided into 5 interval dimensions according to its average value, and the scores are: 20, 18, 16, 14, 12 in sequence; the corresponding purification duration intervals are: [35, 40), [30, 35), [25, 30), [20, 25), [15, 20]. The number of unit transients can implement a point deduction system according to the unit transients. Among them, when the transient load is reduced to 50%, 0.1 point is deducted each time; when the unit is out of service / temporarily stopped and oxidation purification is not carried out, 0.5 point is deducted each time. The peak value of the oxidation Co-60 during the major overhaul can be divided into 5 interval dimensions according to its average value, and the scores are: 15, 13, 11, 9, 7 in sequence; the corresponding Co-60 intervals are: [1000, 1500), [1500, 2000), [2000, 2500), [2500, 3000), [3000, 3500].

[0052] According to Figure 3 the assignment rules, the present invention generates a unit source term file in digital form through 7 dimensions such as the radiation index in the very low water level area of each unit, the manufacturer of the steam generator (evaporator) heat transfer tubes, the fuel cycle length (equivalent full power days), fuel defects or neutron source breakages, the unit purification duration, the number of unit transients, and the peak value of the oxidation Co-60 during the major overhaul, to reflect the historical source term level of the unit and provide a basis for subsequent source term level analysis. Among them, the unit source term file includes the specific scores of each dimension and the original score of the source term comprehensive evaluation index.

[0053] Step S102: Obtain each evaluation dimension, and perform point deduction / plus point assignment based on each evaluation dimension to obtain the score of the source term comprehensive evaluation index.

[0054] Optionally, in the embodiments of the present invention, each evaluation dimension includes: the comprehensive evaluation dimension of daily source items, the comprehensive evaluation dimension of source items for minor repairs during non-refueling outages, the comprehensive evaluation - unit control dimension of source items for major overhauls, and the comprehensive evaluation dimension of good practices or measures. Among them, the comprehensive evaluation dimension of daily source items, the comprehensive evaluation dimension of source items for minor repairs during non-refueling outages, and the comprehensive evaluation - unit control dimension of source items for major overhauls are deduction dimensions, and the comprehensive evaluation dimension of good practices or measures is an addition dimension. Moreover, the deduction proportion of the comprehensive evaluation dimension of daily source items is 5%, the deduction proportion of the comprehensive evaluation dimension of source items for minor repairs during non-refueling outages is 10%, and the deduction proportion of the comprehensive evaluation - unit control dimension of source items for major overhauls is 85%.

[0055] Specifically, the comprehensive evaluation index of source items is used for the assignment evaluation of the entire fuel cycle of the unit. Its initial total score is 100 points. Through three deduction dimensions, namely, the comprehensive evaluation index dimension of normal source items (5%), the comprehensive evaluation index dimension of source items for minor repairs during non-refueling outages (10%), and the comprehensive evaluation index - unit control dimension of source items for major overhauls (85%), and at the same time, combined with the addition dimension of the comprehensive evaluation dimension of good practices or measures for addition assignment, the score of the comprehensive evaluation index of source items is finally obtained. Among them, for the comprehensive evaluation dimension of good practices or measures, according to the good application in the entire fuel cycle process, addition assignment is carried out by adding 1 - 10 points / item according to the contribution degree.

[0056] In the embodiments of the present invention, after obtaining the score of the final comprehensive evaluation index of source items through deduction / addition assignment using the above four evaluation dimensions, the control effect of the source items of this fuel cycle can be evaluated based on the score of the comprehensive evaluation index of source items. At the same time, the basic source item level of the unit in the unit source item file can also be dynamically maintained according to the score of the obtained comprehensive evaluation index of source items (STCEI), as shown in Table 1 below.

[0057] Table 1

[0058]

[0059] As can be seen from Table 1, when the score of the comprehensive evaluation index of source items is between 90 - 100 points, it can be determined that the source item status of the current unit is excellent, that is, the control effect is excellent; when the score of the comprehensive evaluation index of source items is between 80 - 90 points, it can be determined that the source item status of the current unit is good, that is, the control effect is good; when the score of the comprehensive evaluation index of source items is between 70 - 80 points, it can be determined that the source item status of the current unit is acceptable, that is, the control effect is acceptable; when the score of the comprehensive evaluation index of source items is between 60 - 70 points, it can be determined that the source item status of the current unit is unacceptable. At this time, a long-term action plan needs to be formulated; when the score of the comprehensive evaluation index of source items is between 0 - 60 points, it can be determined that the source item status of the current unit is very poor. At this time, an improvement plan needs to be immediately formulated and implemented.

[0060] As shown in Table 1, if the score of the comprehensive evaluation index of the source item is between 90 and 100 points, then update the original score of the comprehensive evaluation index of the source item in the source item file of the unit, that is, add 2 points to the original score of the comprehensive evaluation index of the source item; if the score of the comprehensive evaluation index of the source item is between 80 and 90 points, then update the original score of the comprehensive evaluation index of the source item in the source item file of the unit, that is, add 1 point to the original score of the comprehensive evaluation index of the source item; if the score of the comprehensive evaluation index of the source item is between 70 and 80 points, then do not update the original score of the comprehensive evaluation index of the source item in the source item file of the unit, that is, do not add points to the original score of the comprehensive evaluation index of the source item; if the score of the comprehensive evaluation index of the source item is between 60 and 70 points, then update the original score of the comprehensive evaluation index of the source item in the source item file of the unit, that is, subtract 1 point from the original score of the comprehensive evaluation index of the source item; if the score of the comprehensive evaluation index of the source item is between 0 and 60 points, then update the original score of the comprehensive evaluation index of the source item in the source item file of the unit, that is, subtract 2 points from the original score of the comprehensive evaluation index of the source item.

[0061] Step S103: Perform statistical calculations based on the radiation indices of each sub-region of each unit to obtain the radiation index of the overhaul region.

[0062] In the embodiment of the present invention, the radiation index of the overhaul region is determined by the radiation indices in each state of the unit. Among them, the radiation index values in each state of the unit can be calculated by the following formula:

[0063] X = ∑X i (1).

[0064] In formula (1), X i represents the radiation index of each sub-region in each state of the unit, and X represents the radiation index in each state of the unit.

[0065] Specifically, in the embodiments of the present invention, first, the radiation indices of each sub-region of each unit are determined, and then statistical calculations are performed based on the radiation indices of each sub-region to obtain the radiation index of the overhaul region. As shown in Table 2 below, Y101 refers to the unit with unit number 101. The calculation of its radiation index involves a total of 3 states, namely the state 6 hours after hot shutdown, the state at the end of oxidation purification, and the state of extremely low water level. Each unit state includes: R145 or R185A(3), R144 or R184B(2), RX - 3.4m beside the safety injection tank C(3), RX0m inner ring hall D(5), RX0m outer ring corridor E(4), RX5m hall G(4), RX8m GVG(4), RX11m GV room H(5), RX11m main pump room J(3), a total of 9 sub-regions. The radiation indices of each sub-region in each unit state (the state 6 hours after hot shutdown, the state at the end of oxidation purification, the state of extremely low water level) are shown in Table 2 (for example, in the state 6 hours after hot shutdown: the radiation index of the R145 or R185A(3) region is 88.7, the radiation index of the R144 or R184B(2) region is 1.6, the radiation index of the RX - 3.4m beside the safety injection tank C(3) region is 0.6, the radiation index of the RX0m inner ring hall D(5) region is 45.1, the radiation index of the RX0m outer ring corridor E(4) region is 24.07, the radiation index of the RX5m hall G(4) region is 250.0, the radiation index of the RX8m GVG(4) region is 40.7, the radiation index of the RX11m GV room H(5) region is 144.0, the radiation index of the RX11m main pump room J(3) region is 21.5). Then, by summing up and averaging the radiation indices of each sub-region, the radiation region index in the state of hot shutdown for 6 hours of the unit can be obtained as: 68.5; similarly, the radiation region index in the state at the end of oxidation purification of the unit can be calculated as: 116.9, and the radiation region index in the state of extremely low water level of the unit is: 112.0, as shown in Table 2. Finally, the radiation index of the overhaul region is determined according to the radiation region indices of each unit state. It should be noted that in practical applications, the impacts of the states 6 hours after hot shutdown and at the end of oxidation purification of the unit are relatively small and can generally be ignored. Therefore, the radiation region index in the state of extremely low water level of the unit can be equivalently regarded as the radiation index of the overhaul region.

[0066] Table 2

[0067]

[0068] Step S104: Perform weighted processing on the radiation index of the overhaul region to obtain the radiation weighted value of the overhaul region.

[0069] Optionally, in the embodiments of the present invention, the weighted processing of the radiation index of the overhaul area to obtain the radiation weighted value of the overhaul area includes: determining each sub-area of the overhaul area and obtaining the radiation index of each sub-area; determining the man-hour weight of the radiation index of each sub-area; calculating according to the man-hour weight of the radiation index of each sub-area and the radiation index of each sub-area to obtain the radiation weighted value of the overhaul area. Wherein, the man-hour weight can be determined according to the number of on-site maintenance personnel and the maintenance man-hours, and the number of on-site maintenance personnel and the maintenance man-hours can be directly obtained from the overhaul plan.

[0070] In the embodiments of the present invention, the radiation weighted value of the overhaul area is determined by the radiation weighted values in each state of the unit. Among them, the radiation weighted value in each unit state can be calculated by the following formula:

[0071] X ` = ∑X i ` (2).

[0072] In formula (2), X i ` represents the radiation weighted value of each sub-area in each unit state, and X ` represents the radiation weighted value in each unit state.

[0073] Specifically, as shown in Table 2, after determining the radiation indices of each sub-region, the radiation indices of each sub-region are weighted according to the determined man-hour weights to obtain the radiation weighted values of each sub-region, and finally the radiation weighted values under each unit state (i.e., the weighted radiation indices in Table 2) are obtained. As shown in Table 2, the man-hour weight of the R145 or R185A(3) region is 0.02, the man-hour weight of the R144 or R184B(2) region is 0.02, the man-hour weight of the RX-3.4m safety injection tank side C(3) region is 0.15, the man-hour weight of the RX0m inner ring hall D(5) region is 0.3, the man-hour weight of the RX0m outer ring corridor E(4) region is 0.15, the radiation index of the RX5m hall G(4) region is 0.05, the man-hour weight of the RX8m GVG(4) region is 0.05, the man-hour weight of the RX11m GV room H(5) region is 0.03, and the radiation index of the RX11m main pump room J(3) region is 0.025. Multiplying the man-hour weights of each sub-region directly by their radiation indices can obtain the radiation weighted values of each sub-region. Finally, summing up the radiation weighted values of each sub-region can obtain the radiation weighted values under each unit state. For example, taking the state 6 hours after the unit is in hot shutdown as an example, after the man-hour weight treatment, the radiation weighted value of the R145 or R185A(3) region is 1.8, the radiation weighted value of the R144 or R184B(2) region is 0.0, the radiation weighted value of the RX-3.4m safety injection tank side C(3) region is 0.1, the radiation weighted value of the RX0m inner ring hall D(5) region is 13.5, the radiation weighted value of the RX0m outer ring corridor E(4) region is 3.6, the radiation weighted value of the RX5m hall G(4) region is 12.5, the radiation weighted value of the RX8m GVG(4) region is 1.2, the radiation weighted value of the RX11m GV room H(5) region is 4.3, and the radiation index of the RX11m main pump room J(3) region is 5.4. Then the radiation weighted value in the hot shutdown state for 6 hours is: 1.8 + 0.0 + 0.1 + 13.5 + 3.6 + 12.5 + 1.2 + 4.3 + 5.4 = 42.4. Similarly, the radiation weighted value in the state after oxidation purification is completed can be calculated as: 109.7, and the radiation weighted value in the low-low water level state is: 50.3. It should be noted that in actual applications, the impacts of the unit states of 6 hours after hot shutdown and after oxidation purification are relatively small and can generally be ignored. Therefore, the radiation weighted value in the low-low water level state of the unit can be equivalent to the radiation weighted value of the overhaul area.

[0074] Based on the regional radiation index, the present invention adds the working-hour weight to each sub-region under each unit state to calculate the radiation weighted value of each sub-region, and finally determines the radiation weighted value of the overhaul region. This method can achieve the weight correction for each sub-region, take into account the overall influence of the radiation level and working hours of each sub-region, avoid the interference of the region with less working hours on the source term evaluation, and thus be more targeted and have higher accuracy.

[0075] Step S105: Predict the dose level of the overhaul collective dose based on the radiation weighted value of the overhaul region.

[0076] Specifically, as Figure 4 shown, in the embodiment of the present invention, after determining the radiation weighted value of the overhaul region according to step S104, the dose level of the overhaul collective dose (i.e., the collective dose per unit working hour of the overhaul) can be predicted based on the radiation weighted value of the overhaul region. Among them, the collective dose per unit working hour of the overhaul includes five dose levels: the first dose level, the second dose level, the third dose level, the fourth dose level, and the fifth dose level. When the radiation weighted value of the overhaul region is in the first interval (≤ 350 man.mSv), the collective dose per unit working hour of the overhaul is the first dose level (≤ 4.5 μSv / h); when the radiation weighted value of the overhaul region is in the second interval ((350, 450], unit: man.mSv), the collective dose per unit working hour of the overhaul is the second dose level ((4.5, 5.5]); when the radiation weighted value of the overhaul region is in the third interval ((450, 550], unit: man.mSv), the collective dose per unit working hour of the overhaul is the third dose level ((5.5, 6.5]); when the radiation weighted value of the overhaul region is in the fourth interval ((550, 650], unit: man.mSv), the collective dose per unit working hour of the overhaul is the fourth dose level ((6.5, 7.5]); when the radiation weighted value of the overhaul region is in the fifth interval ((650, 750], unit: man.mSv), the collective dose per unit working hour of the overhaul is the fifth dose level (greater than 7.5 microsievert per hour). Among them, "(" means not including; "]" means including and equal to.

[0077] Step S106: Analyze based on the score of the source term comprehensive evaluation index and the dose level of the overhaul collective dose to determine the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose.

[0078] Specifically, in the embodiments of the present invention, after quickly predicting the dose level of the overhaul collective dose based on the radiation weighting value through step S105, the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose can be obtained through the accumulation and analysis of the large data of the group of reactors. That is, the scores of the source term comprehensive evaluation index and the dose levels of the overhaul collective dose for multiple overhauls are collected, and then the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose is analyzed. Among them, the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose is shown in Table 3.

[0079] Table 3

[0080]

[0081] Step S107: Dynamically maintain the unit source term file according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose and provide a control strategy.

[0082] Specifically, as Figure 5 shown, by analyzing the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose, source term self-evaluation and anomaly investigation can be carried out, and source term optimization measures can be given in advance. At the same time, through the scores of the source term comprehensive evaluation index, the unit source term file is dynamically maintained, providing data input for the medium- and long-term planning of overhauls and the daily source term control, and providing source term control strategies and responses.

[0083] Reference Figure 6 , Figure 6 is the logic block diagram of a comprehensive evaluation device for nuclear power plant source term control provided by the present invention.

[0084] As Figure 6 shown, the comprehensive evaluation device for nuclear power plant source term control includes:

[0085] A source term file construction unit 601, configured to obtain parameter data of each unit in multiple dimensions, and generate a unit source term file based on the analysis and processing of the parameter data.

[0086] A source comprehensive evaluation index tracking unit 602, configured to obtain each evaluation dimension, and perform point deduction / plus point assignment based on each evaluation dimension to obtain the score of the source term comprehensive evaluation index.

[0087] A regional radiation index determination unit 603, configured to perform statistical calculation according to the radiation indexes of each sub-region of each unit to obtain the radiation index of the overhaul region.

[0088] A weight correction unit 604, configured to perform weighted processing on the radiation index of the overhaul region to obtain the radiation weighting value of the overhaul region.

[0089] The overhaul collective dose assessment unit 605 is used to predict the dose level of the overhaul collective dose based on the radiation weighting value of the overhaul area.

[0090] The association relationship determination unit 606 is used to analyze based on the score of the source term comprehensive evaluation index and the dose level of the overhaul collective dose, and determine the corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose.

[0091] The dynamic maintenance and strategy output unit 607 is used to dynamically maintain the unit source term file and provide control strategies according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose.

[0092] Specifically, the specific cooperation operation process among the units in the comprehensive evaluation device for nuclear power plant source term control here can specifically refer to the above-mentioned comprehensive evaluation method for nuclear power plant source term control, which will not be elaborated here.

[0093] The present invention sorts out the historical source term control information of the unit, comprehensively reflects the basic level of the unit's source term from 7 dimensions such as the radiation index in the unit's very low water level area, the manufacturer of steam generator heat transfer tubes, the fuel cycle length (equivalent full power days), fuel defects or neutron source breakage, the unit purification duration, the number of unit transients, and the peak value of oxidation Co-60 during overhaul, and can establish a unit source term file. Through the STCEI index, a score evaluation is carried out on the entire fuel cycle of the unit, and scores are assigned item by item for the unit source term control, which can better reflect the fineness of control. The weighted radiation index can fully reflect the contribution of working hours to the dose area, and can better reflect the contribution degree of specific work and specific area to the overhaul radiation dose. By accumulating big data and exploring the relationship between the overhaul collective dose and the source term comprehensive evaluation index (STCEI), a response strategy for source term control can be given in advance. Through the unit source term control status assigned scores by STCEI, the unit source term file is dynamically maintained, which is beneficial to comparing the control effects of the unit source term.

[0094] In addition, an electronic device of the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement the comprehensive evaluation method for nuclear power plant source term control as described in any one of the above. Specifically, according to the embodiments of the present invention, the process described above with reference to the flowchart can be implemented as a computer software program. For example, an embodiment of the present invention includes a computer program product, which includes a computer program carried on a computer-readable medium, and the computer program contains program codes for executing the method shown in the flowchart. In such an embodiment, when the computer program is downloaded and installed through the electronic device and executed, it executes the above functions defined in the method of the embodiments of the present invention. The electronic device in the present invention can be a terminal such as a notebook, a desktop computer, a tablet computer, a smart phone, etc., or a server.

[0095] In addition, a storage medium of the present invention stores a computer program, and when the computer program is executed by a processor, it implements the comprehensive evaluation method for the source term control of a nuclear power plant as described in any one of the above. Specifically, it should be noted that the storage medium of the present invention described above can be a computer-readable signal medium, a computer-readable storage medium, or any combination of the two. The computer-readable storage medium can be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any combination of the above. More specific examples of the computer-readable storage medium can include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the above. In the present invention, the computer-readable storage medium can be any tangible medium that contains or stores a program, and this program can be used by or in combination with an instruction execution system, apparatus, or device. In the present invention, the computer-readable signal medium can include a data signal propagated in a baseband or as part of a carrier wave, in which the computer-readable program code is carried. Such a propagated data signal can take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination of the above. The computer-readable signal medium can also be any computer-readable medium other than the computer-readable storage medium, and this computer-readable signal medium can send, propagate, or transmit a program for use by or in combination with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium can be transmitted by any suitable medium, including but not limited to: wires, optical cables, RF (radio frequency), etc., or any suitable combination of the above.

[0096] The above computer-readable medium can be included in the above electronic device; or it can exist separately and not be assembled into the electronic device.

[0097] The various embodiments in this specification are described in a progressive manner. Each embodiment focuses on the differences from other embodiments. For the same or similar parts among the various embodiments, reference can be made to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and reference can be made to the description in the method part for the relevant parts.

[0098] Those skilled in the art may further realize that the units and algorithm steps of each example described in combination with the embodiments disclosed herein can be implemented by electronic hardware, computer software, or a combination of the two. To clearly illustrate the interchangeability of hardware and software, the composition and steps of each example have been generally described according to functions in the above description. Whether these functions are executed in a hardware or software manner depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered to exceed the scope of the present invention.

[0099] The steps of the methods or algorithms described in combination with the embodiments disclosed herein can be directly implemented by hardware, software modules executed by a processor, or a combination of the two. The software modules can be placed in a random access memory (RAM), internal memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0100] The above embodiments are only for illustrating the technical concept and features of the present invention, and the purpose is to enable those skilled in the art to understand the content of the present invention and implement it accordingly, and cannot limit the protection scope of the present invention. All equivalent changes and modifications made to the scope of the claims of the present invention shall fall within the scope covered by the claims of the present invention.

Claims

1. A comprehensive evaluation method for source term control of a nuclear power plant, characterized in that: The following steps are involved: Acquire parameter data of multiple dimensions of each unit, and generate a unit source item file based on analysis and processing of the parameter data; Obtaining each evaluation dimension, and assigning points based on each evaluation dimension to obtain the score of the comprehensive evaluation index of the source item; Statistical calculation is performed based on the radiation index of each sub-area of ​​each unit to obtain the radiation index of the overhaul area; Performing weighted processing on the radiation index of the overhaul area to obtain a radiation weighted value of the overhaul area; Predicting a dose level of an overhaul collective dose based on a radiation weighted value of the overhaul area; Performing analysis based on the score of the source term comprehensive evaluation index and the dose level of the overhaul collective dose, determining a corresponding relationship between the source term comprehensive evaluation index and the overhaul collective dose; The source term file of the unit is dynamically maintained and a control strategy is provided according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose.

2. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 1, characterized in that: The parameter data of multiple dimensions of each unit include: low water level area radiation index, evaporator heat transfer tube manufacturer, fuel cycle length, fuel defect number, unit purification time, unit transient number and overhaul oxidation Co-60 peak.

3. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 1, characterized in that: The obtaining of parameter data of multiple dimensions of each unit and generating a unit source item file by analyzing and processing the parameter data includes: Analyze and calculate the parameter data of the multiple dimensions respectively to determine the division interval of each dimension; The scoring method is used to assign values ​​to the divided intervals of each dimension to obtain the basic source level of the unit; The source term profile of the unit is constructed based on the basic source term level of the unit and the scores of the divided areas of each dimension.

4. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 2, characterized in that: The unit source item archive includes: a single unit source item archive and / or a multi-unit source item archive.

5. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 1, characterized in that: The various evaluation dimensions include: comprehensive evaluation dimension of daily source items, comprehensive evaluation dimension of non-refueling shutdown minor maintenance source items, comprehensive evaluation dimension of overhaul source items - unit control dimension and comprehensive evaluation dimension of good practices or measures.

6. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 1, characterized in that: The step of performing weighted processing on the radiation index of the overhaul area to obtain a radiation weighted value of the overhaul area includes: Determine each sub-area of ​​the overhaul area, and obtain the radiation index of each sub-area; Determining the man-hour weight of the radiation index of each sub-area; A radiation weighted value of the overhaul area is obtained by performing calculations based on the man-hour weights of the radiation indexes of the sub-areas and the radiation indexes of the sub-areas.

7. The comprehensive evaluation method for source term control of a nuclear power plant according to claim 5, characterized in that: The comprehensive evaluation dimension of daily source items, the comprehensive evaluation dimension of non-refueling shutdown minor maintenance source items and the comprehensive evaluation dimension of overhaul source items-unit control are deduction dimensions, and the comprehensive evaluation dimension of good practices or initiatives is a bonus dimension. The deduction ratio of the comprehensive evaluation dimension of daily source items is 5%, the deduction ratio of the comprehensive evaluation dimension of non-refueling shutdown minor maintenance source items is 10%, and the deduction ratio of the comprehensive evaluation dimension of overhaul source items-unit control is 85%.

8. A comprehensive evaluation device for source term control of a nuclear power plant, characterized in that: include: A source item archive construction unit is used to obtain parameter data of multiple dimensions of each unit, and to generate a unit source item archive based on the analysis and processing of the parameter data; A source comprehensive evaluation index tracking unit is used to obtain each evaluation dimension, and deduct / add points based on each evaluation dimension to obtain the score of the source item comprehensive evaluation index; A regional radiation index determination unit is used to perform statistical calculations based on the radiation index of each sub-region of each unit to obtain the radiation index of the overhaul region; A weight correction unit, used for performing weighted processing on the radiation index of the overhaul area to obtain a radiation weighted value of the overhaul area; An overhaul collective dose assessment unit, used for predicting a dose level of the overhaul collective dose based on a radiation weighted value of the overhaul area; an association relationship determination unit, configured to perform analysis based on the score of the source item comprehensive evaluation index and the dose level of the overhaul collective dose, and determine the correspondence between the source item comprehensive evaluation index and the overhaul collective dose; A dynamic maintenance and strategy output unit is used to dynamically maintain the source term file of the unit and provide a control strategy according to the corresponding relationship between the source term comprehensive evaluation index and / or the overhaul collective dose.

9. A storage medium, characterized in that: The storage medium stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the comprehensive evaluation method for source term control of a nuclear power plant as described in any one of claims 1 to 7.

10. An electronic device, characterized in that: It comprises a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the comprehensive evaluation method for source term control of a nuclear power plant as claimed in any one of claims 1 to 7 by calling the computer program stored in the memory.

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