阅读说明：本技术 一种核电厂压力温度限值实时监测系统 (Real-time monitoring system for pressure and temperature limit of nuclear power plant ) 是由 陶宏新 贺寅彪 刘畅 李晨 于 2021-08-18 设计创作，主要内容包括：本发明涉及核电厂检测技术领域,具体公开了一种核电厂压力温度限值实时监测系统,包括运行限制曲线绘制模块、数据采集模块、数据处理模块以及数据输出模块,所述数据处理模块与运行限制曲线绘制模块、数据采集模块、数据输出模块相互连接；所述运行限制曲线绘制模块绘制反应堆冷却剂运行限值曲线图,通过数据采集模块采集温度与压力数据,数据处理模块将温度与压力数据在运行限值曲线图中显示出来,最后通过数据输出模块输出数据,为后续脆性断裂分析计算提供技术支持；本发明能够在发生超限瞬态时根据运行年限快速初步判断反应堆冷却剂压力边界是否可接受,并自动生成超限瞬态压力温度时程数据为后续脆性断裂分析计算提供技术支持。(The invention relates to the technical field of nuclear power plant detection, and particularly discloses a nuclear power plant pressure and temperature limit real-time monitoring system which comprises an operation limit curve drawing module, a data acquisition module, a data processing module and a data output module, wherein the data processing module is connected with the operation limit curve drawing module, the data acquisition module and the data output module; the operation limit curve drawing module draws a reactor coolant operation limit curve graph, the data acquisition module acquires temperature and pressure data, the data processing module displays the temperature and pressure data in the operation limit curve graph, and the data output module outputs the data to provide technical support for subsequent brittle fracture analysis and calculation; the method can rapidly and preliminarily judge whether the pressure boundary of the reactor coolant is acceptable according to the operation age when the over-limit transient state occurs, and automatically generate the over-limit transient pressure temperature time course data to provide technical support for the subsequent brittle fracture analysis and calculation.)

1. The utility model provides a pressure temperature limit value real-time supervision system of nuclear power plant which characterized in that: the device comprises an operation limit curve drawing module (1), a data acquisition module (2), a data processing module (3) and a data output module (4), wherein the data processing module (3) is connected with the operation limit curve drawing module (1), the data acquisition module (2) and the data output module (4) mutually; the operation limit curve drawing module (1) draws a reactor coolant operation limit curve graph, the data acquisition module (2) acquires temperature and pressure data, the data processing module (3) displays the temperature and pressure data in the operation limit curve graph, and the data output module (4) outputs the data finally to provide technical support for subsequent brittle fracture analysis and calculation.

2. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: the operation limit curve drawing module (1) is used for drawing a reactor coolant pressure-temperature limit curve for each period within a full design life cycle every ten years.

3. The system of claim 2, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: the reactor coolant pressure-temperature limit curve comprises a temperature rise curve graph and a temperature drop curve graph, and a curve at any temperature rise and drop speed is given.

4. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: the data acquisition module (2) comprises a temperature sensor and a pressure sensor, the temperature sensor is arranged at an inlet connecting pipe of the reactor pressure vessel, the pressure sensor is arranged at the position of the voltage stabilizer, and the sampling frequency is determined.

5. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: and when the mean value of the temperature signals captured by the data processing module (3) reaches the range of +/-3 times of the variance of the data acquisition module (2), judging the temperature signals to be abnormal signals, and rejecting the data.

6. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: the data processing module (3) calculates the change rate of the temperature signal in the last hour, and judges that the temperature signal is an unexpected transient state when the temperature change exceeds 56 ℃ in one hour.

7. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: and when the real-time temperature and pressure data of the data processing module (3) exceeds a specified operation limit curve, judging whether the real-time temperature and pressure data exceed the pressure and temperature limit curve of the corresponding year according to the actual full-power year of operation of the nuclear power plant, if the real-time temperature and pressure data do not exceed the pressure and temperature limit curve, judging that the real-time temperature and pressure data exceed the pressure and temperature limit curve of the corresponding year, if the real-time temperature and pressure data do not exceed the pressure and temperature limit curve, judging that the real-time temperature and pressure data exceed the operation limit curve, the real-time temperature and pressure data exceed the pressure and temperature limit curve, and if the real-time temperature and pressure data do not exceed the pressure and temperature limit curve, the real-power year, the real-time temperature and pressure data exceed the operation limit curve.

8. The system of claim 1, wherein the system is configured to monitor the pressure and temperature limits of the nuclear power plant in real time: and the data output module (4) outputs pressure temperature time-course data to the event exceeding the operation limit value and the event judged as an unexpected transient state and automatically carries out transient linearization processing.

Technical Field

The invention relates to the technical field of nuclear power plant detection, in particular to a real-time monitoring system for pressure and temperature limits of a nuclear power plant.

Background

The nuclear power plant safety analysis report specifications specify reactor coolant system pressure and temperature (P-T) limits, and the pressure and temperature profiles specify allowable ranges for normal operation. These curves are typically used as operating guidance during warm-up or cool-down operations when the plant primary circuit pressure and temperature indications can be monitored to determine whether operation is within allowable limits.

Nuclear power plant operation may occur in the event of exceeding the operating limits of pressure-temperature (P-T), and violation of the operating limits may result in brittle failure of the reactor coolant pressure boundary, and may result in an uninsulated leak or loss of coolant accident. It is therefore not only required to bring operation back within limits in a short period of time, but an evaluation is also required to determine whether the reactor coolant system can continue to operate.

Disclosure of Invention

The invention aims to provide a real-time monitoring system for pressure and temperature limits of a nuclear power plant, so as to solve the problems in the background technology.

In order to achieve the purpose, the invention provides the following technical scheme: a real-time monitoring system for the pressure and temperature limit value of a nuclear power plant comprises an operation limit curve drawing module, a data acquisition module, a data processing module and a data output module, wherein the data processing module is connected with the operation limit curve drawing module, the data acquisition module and the data output module; the operation limit curve drawing module draws a reactor coolant operation limit curve graph, the data acquisition module acquires temperature and pressure data, the data processing module displays the temperature and pressure data in the operation limit curve graph, and the data output module outputs the data finally to provide technical support for subsequent brittle fracture analysis and calculation.

Preferably, the operational limit profiling module plots reactor coolant pressure-temperature limit curves for each period, as a cycle every decade through a full design life cycle.

Preferably, the reactor coolant pressure-temperature limit curve includes a ramp-up curve and a ramp-down curve, as a cycle every ten years over the full design life cycle.

Preferably, the data acquisition module comprises a temperature sensor and a pressure sensor, the temperature sensor is arranged at an inlet connecting pipe of the reactor pressure vessel, the pressure sensor is arranged at the position of the voltage stabilizer, and the sampling frequency is determined.

Preferably, when the mean value of the temperature signals captured by the data processing module reaches the range of +/-3 times of the variance of the data acquisition module, the temperature signals are judged to be abnormal signals, and the data are removed.

Preferably, the data processing module calculates the rate of change of the temperature signal in the last hour, and determines an unexpected transient state when the temperature change exceeds 56 ℃ in one hour.

Preferably, when the real-time data of the temperature and the pressure of the data processing module exceeds a specified operation limit curve, whether the real-time data of the temperature and the pressure of the data processing module exceeds the pressure and temperature limit curve of the corresponding year is judged according to the year of the actual full power operation of the nuclear power plant, if the real-time data of the temperature and the pressure of the data processing module does not exceed the pressure and temperature limit curve, the real-time data of the temperature and the pressure of the data processing module exceeds the pressure and temperature limit curve of the corresponding year, the real-time data of the temperature and the pressure of the data processing module exceeds the operation limit curve, the real-time data of the temperature and the pressure of the nuclear power plant is judged to be beyond the pressure and temperature limit curve of the corresponding year, and if the real-time data of the temperature and the pressure of the nuclear power plant does not exceed the operation limit curve, the real-time data of the temperature and the pressure of the nuclear power plant exceeds the specified operation limit curve.

Preferably, the data output module outputs pressure temperature time-course data to the event exceeding the operation limit value and the event judged to be an unexpected transient state, and automatically carries out transient linearization processing.

Compared with the prior art, the invention has the beneficial effects that: the method can intuitively provide the pressure and temperature running track, can quickly and preliminarily judge that the reactor coolant pressure boundary has enough structural integrity according to the running age when the overrun transient state occurs, and automatically generates overrun transient pressure and temperature time-course data to provide technical support for subsequent brittle fracture analysis and calculation.

Drawings

FIG. 1 is a schematic structural view of the present invention;

reference numbers in the figures: 1. an operation limit curve drawing module; 2. a data acquisition module; 3. a data processing module; 4. and a data output module.

Detailed Description

The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.

Referring to fig. 1, the present invention provides a technical solution: a real-time monitoring system for the pressure and temperature limit value of a nuclear power plant comprises an operation limit curve drawing module 1, a data acquisition module 2, a data processing module 3 and a data output module 4, wherein the data processing module 3 is connected with the operation limit curve drawing module 1, the data acquisition module 2 and the data output module 4; the operation limit curve drawing module 1 draws a reactor coolant operation limit curve graph, the data acquisition module 2 acquires temperature and pressure data, the data processing module 3 displays the temperature and pressure data in the operation limit curve graph, and the data output module 4 outputs the data finally to provide technical support for subsequent brittle fracture analysis and calculation.

Further, the operation limit curve drawing module 1 is used for drawing a reactor coolant pressure-temperature limit curve for each decade in the full design life cycle.

Further, the reactor coolant pressure-temperature limit curve includes a temperature rise curve and a temperature fall curve as a cycle every ten years within the full design life cycle.

Further, the data acquisition module 2 comprises a temperature sensor and a pressure sensor, the temperature sensor is arranged at an inlet connection pipe of the reactor pressure vessel, the pressure sensor is arranged at the position of the voltage stabilizer, and the sampling frequency is determined.

Further, when the mean value of the temperature signals captured by the data processing module 3 reaches the range of 2 +/-3 times of the variance of the data acquisition module, the temperature signals are judged to be abnormal signals, and the data are removed.

Further, the data processing module 3 calculates the change rate of the temperature signal in the last hour, and determines that the transient state is not expected when the temperature change exceeds 56 ℃ in one hour.

Further, when the real-time temperature and pressure data of the data processing module 3 exceeds a specified operation limit curve, whether the real-time temperature and pressure data exceed the pressure and temperature limit curve of the corresponding year is judged according to the actual full-power year of operation of the nuclear power plant, if the real-time temperature and pressure data do not exceed the pressure and temperature limit curve, the real-time temperature and pressure data exceed the pressure and temperature limit curve of the corresponding year, the real-time temperature and pressure data are judged to be an unexpected transient state.

Further, the data output module 4 outputs pressure temperature time-course data to the event exceeding the operation limit value and the event judged as the unexpected transient state, and automatically carries out transient linearization processing.

The working principle is as follows: the operation restriction curve drawing module 1 determines a plurality of time points within the full design life cycle, and in specific implementation, 10 years can be selected as a cycle, and a reactor coolant pressure-temperature limit curve, specifically including a temperature rise curve and a temperature drop curve, is respectively drawn for each cycle. The data acquisition module 2 is respectively provided with a temperature sensor at each inlet connecting pipe of the reactor pressure vessel, and a pressure sensor is arranged at the position of the voltage stabilizer and determines the sampling frequency. The data processing module 3 accesses the data acquired by the data acquisition module 2 and displays the data in an operation limit value curve graph; for ease of viewing, the data points differ in color by the elapsed time frame; when the mean value of the temperature signals captured by the monitoring data reaches the variance of 2 +/-3 times of the data acquisition module, judging the temperature signals to be abnormal signals, and removing the data; calculating the change rate of the temperature signal in the last hour, and judging as an unexpected transient state when the temperature change exceeds 56 ℃ in one hour; if the real-time temperature and pressure data show that the real-time temperature and pressure data exceed the specified operation limit curve, judging whether the real-time temperature and pressure data exceed the pressure and temperature limit curve of the corresponding year according to the actual full-power year of operation of the nuclear power plant, and if the real-time temperature and pressure data do not exceed the pressure and temperature limit curve, judging that the real-time temperature and pressure data exceed the operation limit curve but are acceptable; if the transient state exceeds the predetermined threshold, the transient state is determined to be an unexpected transient state. The data output module 4 outputs pressure temperature time-course data to the event exceeding the operation limit value and the event judged to be an unexpected transient state, automatically carries out transient linearization processing, and provides technical support for subsequent brittle fracture analysis and calculation.

When the over-limit transient occurs, whether the pressure boundary of the reactor coolant is acceptable or not can be rapidly and preliminarily judged according to the operation age, and the over-limit transient pressure temperature time-course data is automatically generated to provide technical support for the subsequent brittle fracture analysis and calculation.

Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that changes, modifications, substitutions and alterations can be made in these embodiments without departing from the principles and spirit of the invention, the scope of which is defined in the appended claims and their equivalents.