Nuclear power pipeline prefabrication whole life cycle management system
Patent Information
- Application Number
- CN202611240731.2
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2026-08-17
- Publication Date
- 2026-10-23
- Estimated Expiration
- 2046-08-17
AI Technical Summary
实际生产过程中,受管材热穿孔、冷轧成型工序的精度波动影响,部分管材会出现局部壁厚偏差超标的情况,这类偏差往往难以通过常规外观检测直接识别,却会在热处理过程中引发显著的温度传导差异:厚壁区域升温速率慢、蓄热能力强,薄壁区域升温速率快、降温过程散热更快,最终导致同一根管材不同位置的实际热处理温度出现明显梯度
1.本发明在以往对多个同一炉批号核电管材进行热处理过程中,对核电管材上不同管段的温度进行均匀性分析,筛选出温度非均管材,提取每个温度非均管材在每个热处理过程中的升温阶段数据和降温阶段数据,并进行温度变化对称性比对,确定壁厚差异管材,从而提前筛除温度不均管材,防止晶粒粗大或带状组织缺陷流入后续工序,并且通过进行温度变化对称性比对分析,确定管材壁厚差异对热处理阶段内的温度不均管材的影响关联,为后续在对壁厚差异管材在进行热处理时策略调整提供数据支持。
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Figure CN122799519B_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of pipeline prefabrication technology, specifically to a nuclear power pipeline prefabrication full life cycle management system. Background Technology
[0002] As core components responsible for media transport and pressure bearing in the primary and secondary loop systems of nuclear power plants, the manufacturing quality of nuclear power pipelines directly affects the safety and stability of the entire nuclear power plant operation. Taking the main coolant pipeline of a 1000MW nuclear power unit as an example, the manufacturing process of this type of ultra-thick-walled, large-diameter seamless pipe involves several key steps, including smelting, hot piercing, cold rolling, and multiple rounds of heat treatment. Among these, the heat treatment process is the core step that determines the internal metallographic structure, mechanical properties, and residual stress level of the pipe material.
[0003] In the existing nuclear power pipeline prefabrication system, the heat treatment process generally adopts a unified temperature control mode for the entire furnace. That is, the heating, holding and cooling processes are completed according to the preset overall temperature parameters of the furnace cavity. There is a lack of precise perception and differentiated control capabilities for different sections of individual pipes. In actual production, due to the precision fluctuations of the hot piercing and cold rolling forming processes, some pipes may have local wall thickness deviations that exceed the standard. Such deviations are often difficult to identify directly through conventional visual inspection, but they will cause significant differences in temperature conduction during the heat treatment process: the heating rate of thick-walled areas is slow and the heat storage capacity is strong, while the heating rate of thin-walled areas is fast and the heat dissipation during the cooling process is faster. Ultimately, this leads to a significant gradient in the actual heat treatment temperature of different locations of the same pipe.
[0004] After heat treatment, defective products are screened out through sampling metallographic testing and hydrostatic testing. This post-inspection model has three major shortcomings: First, the inspection coverage is limited, making it difficult to achieve performance traceability across the entire pipe section and location, and it is easy to miss potential minor defects; second, defective products can only be scrapped directly, which greatly increases the production losses of high-cost special materials such as nuclear power pipelines; and third, it is impossible to establish a quantitative correlation mechanism between wall thickness deviation, uneven heat treatment temperature and final quality defects, making it difficult to achieve precise intervention from the source of the process.
[0005] Therefore, the present invention provides a nuclear power pipeline prefabrication full life cycle management system. Summary of the Invention
[0006] The purpose of this invention is to provide a nuclear power plant pipeline prefabrication full life cycle management system to solve the above-mentioned background problems.
[0007] The objective of this invention can be achieved through the following technical solutions: A nuclear power plant pipeline prefabrication full life cycle management system, comprising: Data Acquisition and Traceability Analysis Module: In the past heat treatment process of multiple nuclear power pipes of the same batch, the temperature uniformity of different pipe sections on the nuclear power pipes was analyzed to screen out pipes with non-uniform temperature. The data comparison and differentiation module extracts the heating and cooling data of each non-uniform temperature pipe in each heat treatment process, and compares the symmetry of temperature changes to determine the pipe with different wall thicknesses. Quality Correlation Analysis Module: Obtains the temperature difference and wall thickness difference for each pipe with different wall thickness, performs correlation analysis on the degree of difference, and evaluates the degree of correlation between temperature difference and wall thickness difference; Zone-based temperature control module: When there is a close correlation between temperature difference and wall thickness difference, it obtains the local target power corresponding to different pipe sections on the pipe with different wall thickness, and adjusts the zone-based temperature control strategy for different pipe sections on the pipe with different wall thickness based on the local target power.
[0008] As a further aspect of the present invention, the process of analyzing the temperature uniformity of different pipe sections is as follows: The nuclear power plant pipe is divided into several local monitoring sections. A monitoring temperature point is set on each local monitoring section. The previous monitoring cycle of heat treatment is set and divided into the previous heating monitoring stage and the previous cooling monitoring stage, and then each is divided into several monitoring time points. At each monitoring point during the previous heating and cooling monitoring phases, the temperature of each monitoring point is obtained and used as the local pipe section heating temperature and local pipe section cooling temperature. The standard deviations of the temperature rise and temperature drop of multiple local pipe sections at the same monitoring time point are calculated to obtain the unit pipe section temperature rise analysis value and unit pipe section temperature drop analysis value.
[0009] As a further aspect of the present invention, the selection of pipes with non-uniform temperature is as follows: The average value of the temperature rise analysis of the unit pipe section at all monitoring time points is calculated to obtain the uniform temperature rise analysis value. The average value of the cooling analysis values of the unit pipe section at all monitoring time points is calculated to obtain the uniform cooling analysis value. The uniform temperature analysis value is obtained by summing the uniform temperature analysis values of heating and cooling. If the temperature uniformity analysis value is greater than the temperature uniformity analysis threshold, it is marked as a temperature non-uniform pipe.
[0010] As a further aspect of the present invention, the process of comparing the symmetry of temperature changes is as follows: In the previous temperature rise monitoring phase and the previous temperature drop monitoring phase, the monitoring time point when each monitoring temperature point reached the temperature rise target value and the monitoring time point when each monitoring temperature point reached the temperature drop target value were obtained respectively, and these were used as the actual temperature rise monitoring time point and the actual temperature drop monitoring time point. The time between the actual temperature rise monitoring point and the preset target temperature rise point, and the time between the actual temperature drop monitoring point and the preset target temperature drop point are obtained as the single-point temperature rise lag time and the single-point temperature drop lag time, respectively, to obtain multiple single-point temperature rise lag times and multiple single-point temperature drop lag times. Based on the same monitoring temperature point, the ratio of the single-point cooling lag time to the single-point heating lag time is calculated to obtain the unit lag symmetry analysis value; The average value of the unit lag symmetry analysis values of all monitored temperature points is calculated by summing them to obtain the time lag symmetry analysis value.
[0011] As a further aspect of the present invention, the screening process for pipes with different wall thicknesses is as follows: The ratio of the uniform cooling analysis value to the uniform heating analysis value is calculated to obtain the temperature symmetry analysis value. The symmetric analysis values of time lag and temperature are summed to obtain the symmetric comparison analysis values; If the value of the symmetric comparison analysis is greater than the threshold of the symmetric comparison analysis, it is recorded as a pipe with wall thickness difference.
[0012] As a further aspect of the present invention, the temperature difference is obtained as follows: On pipes with different wall thicknesses, adjacent local monitoring pipe sections are grouped into a set of correlation analysis groups to obtain multiple sets of correlation analysis groups; Within the correlation analysis group, the difference in local pipe temperature between adjacent local monitoring pipe sections at the same monitoring time point is used as the adjacent temperature difference of the unit. The average of all adjacent temperature differences of the units is summed to obtain the temperature difference of a single group. When the same monitoring time point is obtained, the difference in local pipe cooling temperature between adjacent local monitoring pipe sections is taken as the adjacent cooling difference value of the unit. The average value of the temperature drop difference between adjacent units is summed to obtain the temperature drop difference value of a single group. The sum of the temperature difference for a single heating cycle and the temperature difference for a single cooling cycle is used to obtain the temperature difference value for a single cycle.
[0013] As a further aspect of the present invention, the evaluation process for the degree of difference correlation is as follows: Within the correlation analysis group, the difference in wall thickness between adjacent local monitoring pipe sections is obtained as the single group wall thickness difference value. The Pearson correlation coefficient was calculated for the single temperature difference value and single wall thickness difference value corresponding to multiple correlation analysis groups, and the absolute value was taken to obtain the difference correlation analysis value. If the differential association analysis value is greater than the differential association analysis threshold, it is displayed as a differential close association signal.
[0014] As a further aspect of the present invention, the process for obtaining the local power adjustment amount is as follows: For pipes with varying wall thickness, the difference between the actual wall thickness value and the preset wall thickness value corresponding to each locally monitored pipe segment is extracted as the local wall thickness deviation value. The ratio of the local wall thickness deviation value to the preset wall thickness value is calculated to obtain the local wall thickness deviation rate. Using the formula: Local power adjustment amount = Local wall thickness deviation rate × Correlation calibration coefficient.
[0015] As a further aspect of the present invention, the correlation calibration coefficient is obtained as follows: The unit difference coefficient is obtained by calculating the ratio of a single temperature difference value to a single wall thickness difference value. The unit difference coefficients of multiple correlation analysis groups are summed and averaged to obtain the correlation calibration coefficient.
[0016] As a further aspect of the present invention, the process for adjusting the zoned temperature control strategy is as follows: Based on the local target power corresponding to each local monitoring pipe segment, the formula is: Local target power = Base power density × (1 + Local power adjustment amount).
[0017] The beneficial effects of this invention are as follows: 1. In the previous process of heat treatment of multiple nuclear power plant pipes of the same batch, this invention analyzes the temperature uniformity of different pipe sections on the nuclear power plant pipes, screens out pipes with non-uniform temperatures, extracts the heating and cooling stage data of each non-uniform temperature pipe in each heat treatment process, and performs a symmetrical comparison of temperature changes to identify pipes with different wall thicknesses. This allows for the early screening out of pipes with non-uniform temperatures, preventing coarse grains or banded defects from flowing into subsequent processes. Furthermore, by performing a symmetrical comparison analysis of temperature changes, the influence of pipe wall thickness differences on non-uniform temperature pipes during the heat treatment stage is determined, providing data support for subsequent strategy adjustments when heat treating pipes with different wall thicknesses.
[0018] 2. This invention acquires the temperature difference and wall thickness difference of each pipe with varying wall thickness, performs correlation analysis on the degree of difference, and evaluates the correlation between temperature difference and wall thickness difference. When there is a close correlation between temperature difference and wall thickness difference, it acquires the local target power corresponding to different pipe sections on the pipe with varying wall thickness, and adjusts the zoned temperature control strategy for different pipe sections on the pipe with varying wall thickness according to the local target power, so that the actual temperature reached by each pipe section tends to be consistent, effectively avoiding local grain coarsening and stress deformation problems. Moreover, by precisely controlling the temperature, it minimizes the temperature gradient caused by the wall thickness difference, reduces the generation of thermal stress from the source, and thus improves the pass rate of use of pipes with varying wall thickness in the production heat treatment process. Attached Figure Description
[0019] The invention will now be further described with reference to the accompanying drawings.
[0020] Figure 1 This is a functional module diagram of a nuclear power plant pipeline prefabrication full life cycle management system according to the present invention; Figure 2 This is a flowchart of the steps in the nuclear power plant pipeline prefabrication full life cycle management system of the present invention; Figure 3 This is a flowchart of the decision-making process for a nuclear power pipeline prefabrication full life cycle management system in this invention. Detailed Implementation
[0021] To make the technical means, creative features, objectives and effects of this invention easier to understand, the invention will be further described below in conjunction with specific embodiments.
[0022] Example 1
[0023] During the prefabrication process in factories, when heat-treating nuclear power tubing of the same batch, uneven temperature distribution can be detected, even with the same heating power and heating rate. This unevenness may be due to factors such as coarse grains, banded structures, or work hardening at the beginning and end of the tubing, resulting in different thermal conductivity and coefficient of thermal expansion compared to the finer grains in the middle section. It could also be caused by differences in wall thickness tolerances between the beginning / end and middle sections, among other reasons. Therefore, by identifying the distinguishing characteristics corresponding to these causes, and further analyzing the correlation between these characteristics, the heat treatment strategy can be dynamically adjusted during subsequent heat treatments of the same batch of nuclear power tubing based on the pre-determined causes. Figures 1-3 As shown, this embodiment provides a nuclear power plant pipeline prefabrication full life cycle management system, including: Step 1: In the past heat treatment process of multiple nuclear power pipes of the same batch, the temperature uniformity of different pipe sections on the nuclear power pipes was analyzed to screen out pipes with non-uniform temperature. In some embodiments, the nuclear power plant pipe is equally divided into several local monitoring pipe segments along the axial direction, wherein each local monitoring pipe segment has an equal length; A thermocouple is placed at the geometric center of each local monitoring pipe segment as a monitoring temperature point to collect real-time temperature data of the pipe segment during the heat treatment process. Set a previous monitoring cycle for heat treatment, and divide the previous monitoring cycle for heat treatment into a previous heating monitoring stage and a previous cooling monitoring stage; The previous warming monitoring phase and the previous cooling monitoring phase were each divided into several equal monitoring time points, with the duration between adjacent monitoring time points being equal. In the previous temperature rise monitoring phase, at a monitoring time point, the temperature of each monitoring temperature point was obtained as the local pipe section temperature rise temperature, resulting in multiple local pipe section temperature rise temperatures. The standard deviation of the temperature rise of multiple local pipe sections at the same monitoring time point is calculated to obtain the temperature rise analysis value of the unit pipe section. The average value of the temperature rise analysis of the unit pipe section at all monitoring time points is calculated to obtain the uniform temperature rise analysis value. Similarly, during the previous cooling monitoring phase, the temperature of each monitoring point was obtained at a specific monitoring time point, which was used as the local cooling temperature of the pipe section, resulting in multiple local cooling temperatures of the pipe section. The standard deviation of the cooling temperature of multiple local pipe sections at the same monitoring time point is calculated to obtain the cooling analysis value of the unit pipe section. The average value of the cooling analysis values of the unit pipe section at all monitoring time points is calculated to obtain the uniform cooling analysis value. The uniform temperature analysis value is obtained by summing the uniform temperature analysis values of heating and cooling. Understandably, the temperature uniformity analysis value refers to a comprehensive quantitative index that quantifies the overall temperature distribution uniformity of nuclear power tubing of the same batch during the complete heat treatment process. On the one hand, the temperature uniformity analysis value reflects the degree of temperature difference between various local sections of the nuclear power tubing during the heating stage. On the other hand, the temperature uniformity analysis value reflects the degree of temperature difference between various local sections of the nuclear power tubing during the cooling stage. Specifically, the larger the temperature uniformity analysis value, the greater the temperature difference between various local sections of the nuclear power tubing during the heating and cooling stages. Conversely, the smaller the temperature uniformity analysis value, the smaller the temperature difference between various local sections of the nuclear power tubing during the heating and cooling stages. If the temperature uniformity analysis value is greater than the temperature uniformity analysis threshold, it indicates that the temperature difference between the various local pipe sections of the analyzed nuclear power pipe is large during the heating and cooling stages, and is marked as a temperature non-uniform pipe. If the temperature uniformity analysis value is less than or equal to the temperature uniformity analysis threshold, it indicates that the temperature difference between the various local pipe sections of the analyzed nuclear power pipe is small during the heating and cooling stages, and it is marked as a temperature uniform pipe. It should be noted that the temperature uniformity analysis threshold is determined by those skilled in the art based on the temperature uniformity analysis values of qualified finished products in the long-term production of the same type of nuclear power tubing in the factory. The threshold is determined through statistical analysis: usually, the upper boundary of the temperature uniformity analysis value of qualified batches is selected as the threshold to distinguish between qualified and non-uniform tubing. This is mainly used to screen out products with unqualified temperature uniformity in advance, and at the same time, to provide a basis for judgment for subsequent dynamic adjustment of heat treatment process, to ensure that the nuclear power tubing leaving the factory meets the strict quality requirements for nuclear use, and to avoid problems such as grain size and performance that do not meet the standards due to temperature non-uniformity from flowing into the next process.
[0024] Step 2: Extract the heating and cooling data of each non-uniform temperature pipe during each heat treatment process, and compare the symmetry of temperature changes to determine the pipes with different wall thicknesses. It should be noted that the data during the heating phase includes the local pipe section heating temperature, and the data during the cooling phase includes the local pipe section cooling temperature. In some embodiments, during the previous temperature rise monitoring phase, the monitoring time point when each monitoring temperature point reaches the temperature rise target value is obtained as the actual temperature rise monitoring time point; It should be noted that the preset target temperature rise time point refers to the time point at which the pipe section temperature should theoretically reach the target temperature during the temperature rise monitoring stage, determined according to the material, specifications and heat treatment process of the pipe. The time between the actual temperature rise monitoring point and the preset target temperature rise point is obtained as the single-point temperature rise lag time, and multiple single-point temperature rise lag times are obtained. Similarly, during the previous cooling monitoring phase, the monitoring time point when each monitoring temperature point reached the cooling target value was obtained as the actual temperature drop monitoring time point; The time between the actual temperature drop monitoring time point and the preset target temperature drop time point is obtained as the single-point cooling lag time, and multiple single-point cooling lag times are obtained. It should be noted that the preset target temperature drop time point refers to the time point at which the pipe section temperature should theoretically reach the target temperature during the cooling monitoring stage, determined according to the material, specifications and heat treatment process of the pipe. Based on the same monitoring temperature point, the ratio of the single-point cooling lag time to the single-point heating lag time is calculated to obtain the unit lag symmetry analysis value; The average value of the unit lag symmetry analysis of all monitoring temperature points is summed to obtain the time lag symmetry analysis value. The ratio of the uniform cooling analysis value to the uniform heating analysis value is calculated to obtain the temperature symmetry analysis value. The symmetric analysis values of time lag and temperature are summed to obtain the symmetric comparison analysis values; It is understandable that the meaning of the symmetry comparison analysis value is: a quantitative index for measuring the symmetry of temperature change in the same local pipe section during the heat treatment heating and cooling stages of temperature-non-uniform pipe materials. On the one hand, the time lag symmetry analysis value reflects the average degree of time deviation of multiple individual local pipe sections actually reaching the target temperature, and the symmetry in the heating and cooling stages. On the other hand, the temperature symmetry analysis value reflects the symmetry of the temperature non-uniformity of the entire pipe section in the heating and cooling stages. If the symmetry comparison analysis value is larger, it indicates that the average degree of time deviation of multiple individual local pipe sections actually reaching the target temperature is higher in the heating and cooling stages, and the symmetry of the temperature non-uniformity of the entire pipe section in the heating and cooling stages is also higher. If the symmetry comparison analysis value is smaller, it indicates that the average degree of time deviation of multiple individual local pipe sections actually reaching the target temperature is lower in the heating and cooling stages, and the symmetry of the temperature non-uniformity of the entire pipe section in the heating and cooling stages is also lower. If the symmetry comparison analysis value is greater than the symmetry comparison analysis threshold, it indicates that the average degree of time deviation of multiple individual local pipe sections actually reaching the target temperature is relatively high in the heating and cooling stages, and the symmetry of the temperature non-uniformity of the entire pipe section in the two stages of heating and cooling is also relatively high. The pipe material with non-uniform temperature analyzed is recorded as a pipe material with wall thickness difference. If the symmetry comparison analysis value is less than or equal to the symmetry comparison analysis threshold, it indicates that the average degree of time deviation of multiple individual local pipe sections actually reaching the target temperature is low in the heating and cooling stages, and the symmetry of the temperature non-uniformity of the entire pipe section in the heating and cooling stages is also low. The analyzed temperature non-uniform pipe is recorded as a pipe with non-differential wall thickness. It should be noted that the symmetric comparison analysis threshold is determined by those skilled in the art for historical temperature non-uniform pipes that have undergone full-process quality inspection and have clearly distinguished between temperature non-uniformity caused by wall thickness differences and temperature non-uniformity caused by microstructure differences. The corresponding symmetric comparison analysis values are summarized, and the distribution of symmetric comparison analysis values for the two types of cases is statistically analyzed. The intersection of the two types of data distributions is selected as the threshold. The conventional approach is to select the minimum lower boundary of the symmetric comparison analysis value corresponding to the pipe with wall thickness differences to identify the core cause of temperature non-uniformity.
[0025] Specifically, in the previous heat treatment process of multiple nuclear power pipes from the same batch, the temperature uniformity of different pipe sections on the nuclear power pipes was analyzed to screen out pipes with non-uniform temperatures. Data on the heating and cooling stages of each non-uniform temperature pipe in each heat treatment process were extracted, and the temperature change symmetry was compared to identify pipes with different wall thicknesses. This allowed for the early screening out of pipes with non-uniform temperatures, preventing coarse grains or banded defects from flowing into subsequent processes. Furthermore, by performing temperature change symmetry comparison analysis, the influence of pipe wall thickness differences on non-uniform temperature pipes during the heat treatment stage was determined, providing data support for subsequent strategy adjustments when heat treating pipes with different wall thicknesses.
[0026] Example 2
[0027] like Figures 1-3 As shown, this embodiment provides a nuclear power plant pipeline prefabrication lifecycle association system, which also includes: Step 3: Obtain the temperature difference and wall thickness difference for each pipe with different wall thickness, and perform a correlation analysis of the degree of difference to evaluate the degree of correlation between temperature difference and wall thickness difference; In some embodiments, on pipes with different wall thicknesses, adjacent local monitoring pipe segments are grouped into a set of correlation analysis groups to obtain multiple sets of correlation analysis groups; Within the correlation analysis group, the difference in local pipe temperature between adjacent local monitoring pipe sections at the same monitoring time point is used as the adjacent temperature difference value of the unit. The average of the temperature difference between adjacent units is summed to obtain the temperature difference value of a single group. Similarly, when obtaining the same monitoring time point, the difference in local pipe cooling temperature between adjacent local monitoring pipe sections is used as the adjacent cooling difference value of the unit. The average value of the temperature drop difference between adjacent units is summed to obtain the temperature drop difference value of a single group. The sum of the temperature difference for a single heating cycle and the temperature difference for a single cooling cycle is used to obtain the temperature difference value for a single cycle. Within the correlation analysis group, the difference in wall thickness between adjacent local monitoring pipe sections is obtained as the single group wall thickness difference value. The Pearson correlation coefficient was calculated for the single temperature difference value and single wall thickness difference value corresponding to multiple correlation analysis groups, and the absolute value was taken to obtain the difference correlation analysis value. Understandably, the difference correlation analysis value refers to the core indicator that quantifies the linear correlation strength between local wall thickness differences and local temperature differences. If the difference correlation analysis value is larger, it indicates that the linear correlation between wall thickness differences and temperature differences is stronger, that is, the uneven distribution of local wall thickness of the pipe leads to a stronger dominance of uneven temperature distribution during heat treatment. If the difference correlation analysis value is smaller, it indicates that the linear correlation between wall thickness differences and temperature differences is weaker, that is, the uneven distribution of local wall thickness of the pipe leads to a weaker dominance of uneven temperature distribution during heat treatment. If the difference correlation analysis value is greater than the difference correlation analysis threshold, it indicates that the linear correlation between wall thickness difference and temperature difference is strong. That is, the uneven distribution of local wall thickness of the pipe leads to a strong degree of dominance of uneven temperature distribution during heat treatment, which is shown as a close difference correlation signal. If the difference correlation analysis value is less than or equal to the difference correlation analysis threshold, it indicates that the linear correlation between wall thickness difference and temperature difference is weak. That is, the uneven distribution of local wall thickness of the pipe has a weak dominant effect on the uneven temperature distribution during heat treatment. It is displayed as a difference non-close correlation signal, indicating that the wall thickness difference is not the main cause of uneven temperature distribution. At this time, the system automatically marks the pipe as "microstructure difference pipe", generates a prompt message and pushes it to the quality management module. The quality engineer will further analyze the cause based on the metallographic microstructure test results and choose whether to implement a heat treatment strategy with manual intervention.
[0028] Step 4: Given the close correlation between temperature difference and wall thickness difference, obtain the local target power corresponding to different pipe sections on the pipe with different wall thickness, and adjust the zoned temperature control strategy for different pipe sections on the pipe with different wall thickness based on the local target power. In some embodiments, on pipes with varying wall thicknesses, the difference between the actual wall thickness value and the preset wall thickness value corresponding to each locally monitored pipe segment is extracted as a local wall thickness deviation value. The ratio of the local wall thickness deviation value to the preset wall thickness value is calculated to obtain the local wall thickness deviation rate. Using the formula: Local power adjustment amount = Local wall thickness deviation rate × Correlation calibration coefficient; To help with understanding, a positive local wall thickness deviation rate indicates that the monitored section is a thick-walled section; a negative local wall thickness deviation rate indicates that the monitored section is a thin-walled section. The process for obtaining the correlation calibration coefficients is as follows: The unit difference coefficient is obtained by calculating the ratio of a single temperature difference value to a single wall thickness difference value. The unit difference coefficients of multiple correlation analysis groups are summed and averaged to obtain the correlation calibration coefficient. Based on the local target power corresponding to each local monitoring pipe segment, the formula is used: Local target power = Base power density × (1 + Local power adjustment amount). To help with understanding, when the local monitoring section is a thick-walled section, it indicates that the local power adjustment is positive, and the heat treatment power needs to be increased; when the local monitoring section is a thin-walled section, it indicates that the local power adjustment is negative, and the heat treatment power needs to be reduced.
[0029] Specifically, this embodiment involves: acquiring the temperature difference and wall thickness difference for each pipe with varying wall thickness, performing a correlation analysis of the degree of difference, evaluating the correlation between temperature difference and wall thickness difference, and, when a close correlation exists between temperature difference and wall thickness difference, acquiring the local target power corresponding to different pipe segments on the pipe with varying wall thickness, and adjusting the zoned temperature control strategy for different pipe segments based on the local target power, so that the actual temperature reached by each pipe segment tends to be consistent, effectively avoiding local grain coarsening and stress deformation problems. Moreover, by precisely controlling the temperature, the temperature gradient caused by the wall thickness difference is minimized, reducing the generation of thermal stress from the source, thereby improving the pass rate of use of pipes with varying wall thickness during the production heat treatment process.
[0030] The foregoing has provided a detailed description of one embodiment of the present invention, but this description is merely a preferred embodiment and should not be construed as limiting the scope of the invention. All equivalent variations and modifications made within the scope of the present invention should still fall within the scope of the present invention.
Claims
1. A nuclear power plant pipeline prefabrication full life cycle management system, characterized in that: Includes the following modules: Data Acquisition and Traceability Analysis Module: In the past heat treatment process of multiple nuclear power pipes of the same batch, the temperature uniformity of different pipe sections on the nuclear power pipes was analyzed to screen out pipes with non-uniform temperature. The data comparison and differentiation module extracts the heating and cooling data of each non-uniform temperature pipe in each heat treatment process, and compares the symmetry of temperature changes to determine the pipe with different wall thicknesses. Quality Correlation Analysis Module: Obtains the temperature difference and wall thickness difference for each pipe with different wall thickness, performs correlation analysis on the degree of difference, and evaluates the degree of correlation between temperature difference and wall thickness difference; Zone-based temperature control module: When there is a close correlation between temperature difference and wall thickness difference, it obtains the local target power corresponding to different pipe sections on the pipe with different wall thickness, and adjusts the zone-based temperature control strategy for different pipe sections on the pipe with different wall thickness based on the local target power.
2. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 1, characterized in that: The process of analyzing the temperature uniformity of different pipe sections is as follows: The nuclear power plant pipe is divided into several local monitoring sections. A monitoring temperature point is set on each local monitoring section. The previous monitoring cycle of heat treatment is set and divided into the previous heating monitoring stage and the previous cooling monitoring stage, and then each is divided into several monitoring time points. At each monitoring point during the previous heating and cooling monitoring phases, the temperature of each monitoring point is obtained and used as the local pipe section heating temperature and local pipe section cooling temperature. The standard deviations of the temperature rise and temperature drop of multiple local pipe sections at the same monitoring time point are calculated to obtain the unit pipe section temperature rise analysis value and unit pipe section temperature drop analysis value.
3. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 2, characterized in that: The selection criteria for pipes with non-uniform temperature are as follows: The average value of the temperature rise analysis of the unit pipe section at all monitoring time points is calculated to obtain the uniform temperature rise analysis value. The average value of the cooling analysis values of the unit pipe section at all monitoring time points is calculated to obtain the uniform cooling analysis value. The uniform temperature analysis value is obtained by summing the uniform temperature analysis values of heating and cooling. If the temperature uniformity analysis value is greater than the temperature uniformity analysis threshold, it is marked as a temperature non-uniform pipe.
4. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 1, characterized in that: The process of comparing the symmetry of temperature changes is as follows: In the previous temperature rise monitoring phase and the previous temperature drop monitoring phase, the monitoring time point when each monitoring temperature point reached the temperature rise target value and the monitoring time point when each monitoring temperature point reached the temperature drop target value were obtained respectively, and these were used as the actual temperature rise monitoring time point and the actual temperature drop monitoring time point. The time between the actual temperature rise monitoring point and the preset target temperature rise point, and the time between the actual temperature drop monitoring point and the preset target temperature drop point are obtained as the single-point temperature rise lag time and the single-point temperature drop lag time, respectively, to obtain multiple single-point temperature rise lag times and multiple single-point temperature drop lag times. Based on the same monitoring temperature point, the ratio of the single-point cooling lag time to the single-point heating lag time is calculated to obtain the unit lag symmetry analysis value; The average value of the unit lag symmetry analysis values of all monitored temperature points is summed to obtain the time lag symmetry analysis value.
5. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 4, characterized in that: The screening process for pipes with wall thickness differences is as follows: The ratio of the uniform cooling analysis value to the uniform heating analysis value is calculated to obtain the temperature symmetry analysis value. The symmetric analysis values of time lag and temperature are summed to obtain the symmetric comparison analysis values; If the value of the symmetric comparison analysis is greater than the threshold of the symmetric comparison analysis, it is recorded as a pipe with wall thickness difference.
6. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 4, characterized in that: The temperature difference was obtained as follows: On pipes with different wall thicknesses, adjacent local monitoring pipe sections are grouped into a set of correlation analysis groups to obtain multiple sets of correlation analysis groups; Within the correlation analysis group, the difference in local pipe temperature between adjacent local monitoring pipe sections at the same monitoring time point is used as the adjacent temperature difference of the unit. The average of all adjacent temperature differences of the units is summed to obtain the temperature difference of a single group. When the same monitoring time point is obtained, the difference in local pipe cooling temperature between adjacent local monitoring pipe sections is taken as the adjacent cooling difference value of the unit. The average value of the temperature drop difference between adjacent units is summed to obtain the temperature drop difference value of a single group. The sum of the temperature difference for a single heating cycle and the temperature difference for a single cooling cycle is used to obtain the temperature difference value for a single cycle.
7. A nuclear power plant pipeline prefabrication full life cycle management system according to claim 6, characterized in that: The assessment process for the degree of correlation between differences is as follows: Within the correlation analysis group, the difference in wall thickness between adjacent local monitoring pipe sections is obtained as the single group wall thickness difference value. The Pearson correlation coefficient was calculated for the single temperature difference value and single wall thickness difference value corresponding to multiple correlation analysis groups, and the absolute value was taken to obtain the difference correlation analysis value. If the differential association analysis value is greater than the differential association analysis threshold, it is displayed as a differential close association signal.
8. The nuclear power plant pipeline prefabrication full life cycle management system according to claim 1, characterized in that: The process of obtaining the local power adjustment is as follows: For pipes with varying wall thickness, the difference between the actual wall thickness value and the preset wall thickness value corresponding to each locally monitored pipe segment is extracted as the local wall thickness deviation value. The ratio of the local wall thickness deviation value to the preset wall thickness value is calculated to obtain the local wall thickness deviation rate. Using the formula: Local power adjustment amount = Local wall thickness deviation rate × Correlation calibration coefficient.
9. A nuclear power plant pipeline prefabrication full life cycle management system according to claim 8, characterized in that: The correlation calibration coefficients are obtained as follows: The unit difference coefficient is obtained by calculating the ratio of a single temperature difference value to a single wall thickness difference value. The unit difference coefficients of multiple correlation analysis groups are summed and averaged to obtain the correlation calibration coefficient.
10. A nuclear power plant pipeline prefabrication full life cycle management system according to claim 1, characterized in that: The process for adjusting the zone temperature control strategy is as follows: Based on the local target power corresponding to each local monitoring pipe segment, the formula is: Local target power = Base power density × (1 + Local power adjustment amount).
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