阅读说明：本技术 一种核电厂蒸汽发生器的监测方法及系统 (Monitoring method and system for steam generator of nuclear power plant ) 是由 苏锦成 王振中 薛静 吴巧英 贾小攀 谷振杰 贝晨 赵晓山 褚松良 樊彦芳 于 2021-06-11 设计创作，主要内容包括：本发明公开一种核电厂蒸汽发生器的监测方法,包括：建立蒸汽发生器模型,并在所述蒸汽发生器模型内模拟未发生泄漏时的蒸汽发生器内的放射性响应三维分布,以得到模拟的未发生泄漏时的放射性响应三维分布；在蒸汽发生器的内部或外部预设探测点,用于检测所述探测点的实际放射性强度值A-i；根据所述模拟的未发生泄漏时的放射性响应三维分布,确定所述探测点在未发生泄漏时的正常放射性强度值A-(i0)；将实际放射性强度值A-i与正常放射性强度值A-(i0)进行比较,根据A-i与A-(i0)的比较结果判断蒸汽发生器内是否发生泄漏。本发明还公开一种核电厂蒸汽发生器的监测系统。本发明可对蒸汽发生器进行在线监测,能够快速判断蒸汽发生器的传热管是否发生放射性泄漏。(The invention discloses a monitoring method of a steam generator of a nuclear power plant, which comprises the following steps: establishing a steam generator model, and simulating radioactive response three-dimensional distribution in the steam generator when leakage does not occur in the steam generator model to obtain simulated radioactive response three-dimensional distribution when leakage does not occur; presetting a detection point inside or outside the steam generator for detecting the actual radioactivity intensity value A of the detection point i (ii) a According to the simulated three-dimensional distribution of the radioactive response when leakage does not occur, determining the normal radioactive intensity value A of the detection point when leakage does not occur i0 (ii) a The actual radioactivity intensity value A i Intensity value A of normal radioactivity i0 Comparison was made according to A i And A i0 And judging whether leakage occurs in the steam generator or not according to the comparison result. The invention also discloses a monitoring system of the nuclear power plant steam generator. The invention can carry out on-line monitoring on the steam generator and can quickly judge whether the heat transfer pipe of the steam generator has radioactive leakage.)

1. A method of monitoring a nuclear power plant steam generator, comprising:

establishing a steam generator model, and simulating radioactive response three-dimensional distribution in the steam generator when leakage does not occur in the steam generator model to obtain simulated radioactive response three-dimensional distribution when leakage does not occur;

presetting a detection point inside or outside the steam generator for detecting the actual radioactivity intensity value A of the detection point_i；

According to the simulated three-dimensional distribution of the radioactive response when leakage does not occur, determining the normal radioactive intensity value A of the detection point when leakage does not occur_i0；

The actual radioactivity intensity value A_iIntensity value A of normal radioactivity_i0Comparison was made according to A_iAnd A_i0And judging whether leakage occurs in the steam generator or not according to the comparison result.

2. The method of monitoring a nuclear power plant steam generator of claim 1, wherein upon determining that a leak has occurred within the steam generator, the method further comprises:

when heat transfer pipes at different positions in the steam generator are simulated to leak in the steam generator model, corresponding radioactive response three-dimensional distribution in the steam generator is obtained so as to obtain simulated radioactive response three-dimensional distribution when the leak occurs;

according to the simulated three-dimensional distribution of radioactive response during leakage, a plurality of leakage radioactive intensity values B respectively corresponding to the detection points when the heat transfer pipes at different positions are leaked are determined_jk；

The actual radioactivity intensity value A_iWith respective leakage radioactivity intensity value B_jkAre compared separately and according to A_iAnd B_jkThe comparison of (a) locates the location where the leak occurred.

3. A method for monitoring a steam generator of a nuclear power plant according to claim 2, wherein the number of the detection points is plural, and the plural detection points are uniformly distributed at a position below a water level of the steam generator when the reactor is normally operated.

4. A monitoring system of a nuclear power plant steam generator is characterized by comprising a radioactivity detection unit (3), a data processing unit (4) and a user interaction unit (5),

the user interaction unit is internally preset with simulated radioactive response three-dimensional distribution data which are not leaked, and the simulated radioactive response three-dimensional distribution data which are not leaked are transmitted;

the radioactivity detection unit comprises a detection point monitor which is provided withArranged at a probe point inside or outside the steam generator for detecting the actual radioactivity intensity value A of the probe point_iAnd transmits the actual radioactivity intensity value A detected_i；

The data processing unit comprises a first data processing module which is respectively electrically connected with the user interaction unit and the radioactivity detection unit and used for calculating a normal radioactivity intensity value A of the detection point when leakage does not occur according to simulated three-dimensional distribution data of radioactivity response when leakage does not occur, which is transmitted by the user interaction unit_iOThen the actual radioactivity intensity value A transmitted by the radioactivity detection unit_iIntensity value A of normal radioactivity_i0Making a comparison according to A_iAnd A_i0And judging whether leakage occurs in the steam generator or not according to the comparison result.

5. The nuclear power plant steam generator monitoring system of claim 4, further comprising a steam generator model and a simulation unit,

the simulation unit is electrically connected with the user interaction unit and used for simulating the radioactive response three-dimensional distribution in the steam generator when leakage does not occur in the steam generator model so as to obtain the simulated radioactive response three-dimensional distribution data when leakage does not occur and transmit the data to the user interaction unit.

6. The monitoring system of the nuclear power plant steam generator of claim 4 or 5, wherein the user interaction unit is further preset with simulated three-dimensional distribution data of radioactive response when a leak occurs;

the data processing unit further comprises a second data processing module which is respectively electrically connected with the user interaction unit and the radioactivity detection unit and used for calculating a plurality of corresponding detection points when the heat transfer pipes at different positions in the steam generator leak according to the simulated radioactivity response three-dimensional distribution data transmitted by the user interaction unit when the leakage occursIntensity of leaked radioactivity B_jkThen the actual radioactivity intensity value A transmitted by the radioactivity detection unit_iWith respective leakage radioactivity intensity value B_jkMaking a comparison according to A_iAnd B_jkThe comparison of (a) locates the location where the leak occurred.

7. The monitoring system of the nuclear power plant steam generator of claim 6, wherein the user interaction unit further comprises a display module for displaying the determination result output by the first data processing module and the location of the second data processing module where the leakage occurs.

8. The nuclear power plant steam generator monitoring system of claim 6, wherein the simulation unit is further configured to simulate a three-dimensional distribution of radioactive responses in the steam generator corresponding to a leakage of heat transfer tubes at different positions in the steam generator model, so as to obtain the simulated three-dimensional distribution of radioactive responses in the leakage and send the simulated three-dimensional distribution of radioactive responses to the user interaction unit.

9. The nuclear power plant steam generator monitoring system of claim 8, further comprising a storage unit,

the storage unit is electrically connected with the radioactivity detection unit and is used for storing the actual radioactivity intensity value A detected by the radioactivity detection unit_iHistorical data of (a);

the data processing unit further comprises a third data processing module, and the third data processing module is used for obtaining an actual radioactivity intensity value A according to the detection of the radioactivity detection unit_iThe actual three-dimensional distribution of the radioactive response is calculated,

the storage unit is also electrically connected with the third data processing module and is used for storing the historical data of the three-dimensional distribution of the actual radioactive response.

10. The nuclear plant steam generator monitoring system of claim 6, further comprising an alarm unit,

the data processing unit is also electrically connected with the alarm unit and is used for sending an alarm control signal to the alarm unit when the judgment result is that the steam generator is leaked, and the alarm unit is used for giving an alarm according to the alarm control signal of the data processing unit.

Technical Field

The invention belongs to the field of nuclear engineering, and particularly relates to a method and a system for monitoring a steam generator of a nuclear power plant.

Background

The steam generator of a pressurized water reactor nuclear power plant contains thousands of heat transfer tubes inside. The heat transfer tubes are primary circuit boundaries, however, they are radioactive due to activation of the primary circuit coolant or rupture of the cladding. Once the heat transfer tubes leak, radioactivity leaks into the two circuits, which can affect the safe operation of the nuclear power plant.

Currently, it is mainly determined whether the heat transfer pipe leaks (especially when the leakage amount is small) by detecting whether the radioactivity of the steam in the two circuits exceeds a limit value. Moreover, when the leakage is confirmed, the leaked heat transfer pipe needs to be repaired in time. However, because the number of the heat transfer pipes is large, if each heat transfer pipe is detected one by one, the efficiency is low, and the position of the heat transfer pipe with leakage is difficult to be quickly positioned, so that the overhauling process is overlong, and the operation economic benefit of the nuclear power plant is seriously influenced.

Disclosure of Invention

The invention aims to solve the technical problem of the prior art, and provides a monitoring method and a monitoring system for a steam generator of a nuclear power plant, which can perform online monitoring on the steam generator and can quickly judge whether a heat transfer pipe of the steam generator has radioactive leakage.

According to one aspect of the invention, a monitoring method of a nuclear power plant steam generator is provided, and the technical scheme is as follows:

a method of monitoring a nuclear power plant steam generator, comprising:

establishing a steam generator model, and simulating radioactive response three-dimensional distribution in the steam generator when leakage does not occur in the steam generator model to obtain simulated radioactive response three-dimensional distribution when leakage does not occur;

presetting a detection point inside or outside the steam generator for detecting the actual radioactivity intensity value A of the detection point_i；

According to the simulated three-dimensional distribution of the radioactive response when leakage does not occur, determining the normal radioactive intensity value A of the detection point when leakage does not occur_i0；

The actual radioactivity intensity value A_iIntensity value A of normal radioactivity_i0Comparison was made according to A_iAnd A_i0And judging whether leakage occurs in the steam generator or not according to the comparison result.

Preferably, when it is judged that the leakage occurs in the steam generator, the method further includes:

when heat transfer pipes at different positions in the steam generator are simulated to leak in the steam generator model, corresponding radioactive response three-dimensional distribution in the steam generator is obtained so as to obtain simulated radioactive response three-dimensional distribution when the leak occurs;

according to the simulated three-dimensional distribution of radioactivity response when leakage occurs, a plurality of leakage radioactivity corresponding to the heat transfer pipes of the detection points at different positions when leakage occurs are determinedIntensity value B_jk；

The actual radioactivity intensity value A_iWith respective leakage radioactivity intensity value B_jkAre compared separately and according to A_iAnd B_jkThe comparison of (a) locates the location where the leak occurred.

Preferably, the number of the detection points is multiple, and the multiple detection points are uniformly distributed at positions below the water level of the steam generator when the reactor normally operates.

According to another aspect of the invention, a monitoring system of a steam generator of a nuclear power plant is provided, which adopts the technical scheme that:

a monitoring system of a nuclear power plant steam generator comprises a radioactivity detection unit, a data processing unit and a user interaction unit, wherein simulated three-dimensional distribution data of radioactivity response when leakage does not occur are preset in the user interaction unit, and the simulated three-dimensional distribution data of radioactivity response when leakage does not occur are transmitted;

the radioactivity detection unit comprises a detection point monitor which is arranged on a detection point inside or outside the steam generator and is used for detecting the actual radioactivity intensity value A of the detection point_iAnd transmits the actual radioactivity intensity value A detected_i；

The data processing unit comprises a first data processing module which is respectively electrically connected with the user interaction unit and the radioactivity detection unit and used for calculating a normal radioactivity intensity value A of the detection point when leakage does not occur according to simulated three-dimensional distribution data of radioactivity response when leakage does not occur, which is transmitted by the user interaction unit_iOThen the actual radioactivity intensity value A transmitted by the radioactivity detection unit_iIntensity value A of normal radioactivity_i0Making a comparison according to A_iAnd A_i0And judging whether leakage occurs in the steam generator or not according to the comparison result.

Preferably, the system further comprises a steam generator model and a simulation unit, wherein the simulation unit is electrically connected with the user interaction unit and is used for simulating the radioactive response three-dimensional distribution in the steam generator when no leakage occurs in the steam generator model so as to obtain the simulated radioactive response three-dimensional distribution data when no leakage occurs and transmit the simulated radioactive response three-dimensional distribution data to the user interaction unit.

Preferably, the user interaction unit is also preset with simulated radioactive response three-dimensional distribution data when leakage occurs;

the data processing unit further comprises a second data processing module which is respectively electrically connected with the user interaction unit and the radioactivity detection unit and used for calculating a plurality of leakage radioactivity intensity values B corresponding to the detection points when the heat transfer pipes at different positions in the steam generator are leaked according to the simulated radioactivity response three-dimensional distribution data transmitted by the user interaction unit when the leakage occurs_jkThen the actual radioactivity intensity value A transmitted by the radioactivity detection unit_iWith respective leakage radioactivity intensity value B_jkMaking a comparison according to A_iAnd B_jkThe comparison of (a) locates the location where the leak occurred.

Preferably, the user interaction unit further includes a display module, configured to display the judgment result output by the first data processing module and the position of the leakage output by the second data processing module.

Preferably, the simulation unit is further configured to, when a leakage occurs in heat transfer pipes at different positions in the steam generator model, simulate a three-dimensional distribution of radioactive responses in the steam generator corresponding to the leakage, so as to obtain a simulated three-dimensional distribution of radioactive responses in the leakage, and send the simulated three-dimensional distribution of radioactive responses to the user interaction unit.

Preferably, the system further comprises a storage unit electrically connected to the radioactivity detection unit for storing the actual radioactivity intensity value a detected by the radioactivity detection unit_iHistorical data of (a);

the data processing unit further comprises a third data processing module, and the third data processing module is used for detecting the actual radioactivity intensity obtained according to the radioactivity detection unitValue A_iAnd calculating the actual radioactive response three-dimensional distribution, wherein the storage unit is also electrically connected with the third data processing module and is used for storing the historical data of the actual radioactive response three-dimensional distribution.

Preferably, the system further comprises an alarm unit, the data processing unit is further electrically connected with the alarm unit and is used for sending an alarm control signal to the alarm unit when the judgment result is that the steam generator is leaked, and the alarm unit is used for sending an alarm sound according to the alarm control signal of the data processing unit.

The monitoring method and the monitoring system for the steam generator of the nuclear power plant can monitor the steam generator on line and can quickly judge whether the heat transfer pipe of the steam generator leaks radioactivity, so that a worker can overhaul the heat transfer pipe in time, the problem of radioactivity leakage is solved in time, and the operation safety of the nuclear power plant is improved. And furthermore, the position where leakage occurs can be positioned, the maintenance efficiency is improved, the maintenance time and the workload of maintenance personnel are greatly reduced, and the economic benefit of the nuclear power plant is improved.

Drawings

FIG. 1 is a schematic diagram of a monitoring method for a nuclear power plant steam generator according to an embodiment of the present disclosure

FIG. 2 is a schematic diagram of a monitoring system for a nuclear power plant steam generator according to an embodiment of the present disclosure.

In the figure: 1-a steam generator; 2-heat transfer tubes; 3-a radioactivity detecting unit; 4-a data processing unit; 5-user interaction unit.

Detailed Description

In order to make those skilled in the art better understand the technical solution of the present invention, the technical solution of the present invention will be clearly and completely described below with reference to the accompanying drawings, and it is obvious that the described embodiments are a part of the embodiments of the present invention, and not all 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.

In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.

In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implying any number of technical features indicated. Thus, features defined as "first", "second", may explicitly or implicitly include one or more of the described features. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.

In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or through the interconnection of two elements. The specific meaning of the above terms in the present invention can be understood in specific cases for those skilled in the art.

Example 1

As shown in fig. 1, the embodiment discloses a monitoring method for a steam generator of a nuclear power plant, which includes:

s1, establishing a steam generator model, and simulating the radioactive response three-dimensional distribution in the steam generator 1 when no leakage occurs in the steam generator model to obtain the simulated radioactive response three-dimensional distribution when no leakage occurs;

s2, presetting a detection point in the steam generator model for detecting the actual radioactivity intensity value A of the detection point_i；

S3, according to the simulated three-dimensional distribution of the radioactivity response when no leakage occurs, determining the normal radioactivity of the detection point when no leakage occursIntensity value A_i0；

S4, the actual radioactivity intensity value A is calculated_iIntensity value A of normal radioactivity_i0Comparison was made according to A_iAnd A_i0And judging whether the heat transfer pipe in the steam generator leaks or not according to the comparison result.

In particular, when the actual radioactivity intensity value A is_iGreater than normal radioactivity intensity value A_i0If so, determining that the heat transfer pipe 2 in the steam generator 1 leaks; otherwise, no leakage occurs in the heat transfer tubes 2 in the steam generator 1. And, the actual radioactivity intensity value A of the position of the detection point_i0The detection is continuous detection, and whether the heat transfer pipe 2 in the steam generator 1 leaks can be judged in real time, so that on-line monitoring can be realized. In practical operation, the actual radioactivity intensity value A can be processed according to a certain processing frequency according to actual conditions_iIntensity value A of normal radioactivity_i0The comparison is performed so that the amount of data processing can be greatly reduced.

Compared with the prior art, the method can be used for monitoring the steam generator 1 on line and quickly judging whether the heat transfer pipe in the steam generator leaks in radioactivity, so that workers can overhaul the heat transfer pipe in time and the operation safety of a nuclear power plant is ensured.

In some embodiments, upon determining that a leak has occurred within the steam generator, the method further comprises:

s5, when the heat transfer pipes 2 at different positions in the steam generator 1 are simulated to leak in the steam generator model, the corresponding radioactive response three-dimensional distribution in the steam generator 2 is obtained so as to obtain the simulated radioactive response three-dimensional distribution when the leakage occurs;

s6, according to the simulated three-dimensional distribution of radioactivity response when leakage occurs, a plurality of leakage radioactivity intensity values B corresponding to the leakage of the heat transfer pipe 2 with the detection point at different positions are determined_jk；

S7, the actual radioactivity intensity value A is calculated_iWith respective leakage radioactivity intensity value B_jkAre compared separately and according to A_iAnd B_jkIs compared withThe effect locates the location where the leak occurred.

Where j denotes a predetermined location where a leak occurs, j is a positive integer, i.e., j is 1, 2, 3, and_jkindicating the radioactive response intensity at different locations k within the steam generator at which leaks occur at the j location. Generally, the more preset positions j where leakage occurs and the more positions k where simulated radioactive response intensity is selected in the steam generator under the condition of the same preset leakage position j are more beneficial to improving the accuracy of the subsequent positioning of the leakage position. The actual radioactivity intensity value A_iLeakage radioactivity intensity value B corresponding to different positions k in the steam generator when the heat transfer pipe at different positions j leaks_jkComparing one by one when the actual radioactivity intensity value A_iEqual to the leak radioactivity intensity value B_jkWhen it is, then B_jkThe indicated position where the leakage is supposed to occur is the position where the leakage occurs. For example, B₂₃＝A_iIf so, the predetermined position where the leakage occurs, which is represented by j 2, is the position where the leakage occurs.

Considering that in actual operation, there may be a plurality of B_jkEqual to Ai, i.e. the radioactive response of the preset probing point to a plurality of preset leakage positions is the same, and at this time, the leakage position can be further determined by the field detection of workers and the like. For example, if B is present₂₃、B₆₇、B₈₉Are all equal to A_iIf there is a possibility that any of the preset leak positions represented by j 2, 6, and 8 is a leak position, the worker detects the heat transfer tubes at the three positions j 2, 6, and 8 and further specifies the leak position.

Compared with the prior art, the method can also position the position where leakage occurs, can improve the maintenance efficiency, and greatly reduces the maintenance time and the workload of maintenance personnel.

In some embodiments, as shown in fig. 2, the detection point is located below the water level of the steam generator 1 during normal operation of the reactor, and the number of the detection points may be one or more, i.e., i 1, 2, 3.

Specifically, when the number of the preset detection points is multiple, i.e., i is 2, 3, or so, the multiple preset detection points may be distributed inside the steam generator 1, may also be distributed outside the steam generator 1, and may also be partially disposed inside the steam generator 1 and partially disposed outside the steam generator 1. Through setting up a plurality of preset detection points, can improve the degree of accuracy of judgement through the mutual check-up between the result of judging by the monitoring of different preset detection points. When the number of the preset detection points is one, the preset detection points may be distributed inside the steam generator 1 or may be distributed outside the steam generator 1.

The monitoring method for the steam generator of the nuclear power plant can monitor the steam generator on line and can quickly judge whether the heat transfer pipe of the steam generator leaks radioactivity, so that a worker can overhaul the heat transfer pipe in time, the problem of radioactivity leakage can be solved by timely control, and the operation safety of the nuclear power plant can be improved. And furthermore, the position where leakage occurs can be positioned, the maintenance efficiency is improved, the maintenance time and the workload of maintenance personnel are greatly reduced, and the economic benefit of the nuclear power plant is improved.

Example 2

As shown in fig. 2, the present embodiment discloses a monitoring system of a steam generator of a nuclear power plant, which includes a radioactivity detection unit 3, a data processing unit 4, and a user interaction unit 5, wherein:

the user interaction unit 5 is preset with simulated radioactive response three-dimensional distribution data in the steam generator 1 when leakage does not occur so as to obtain simulated radioactive response three-dimensional distribution when leakage does not occur, and the simulated radioactive response three-dimensional distribution data when leakage does not occur is transmitted;

a radioactivity detecting unit 3 including a detecting point monitor disposed at a detecting point inside or outside the steam generator for detecting an actual radioactivity intensity value A of the detecting point_iAnd transmit the detectionTo the actual radioactivity intensity value A_i；

The data processing unit 4 comprises a first data processing module electrically connected to the radioactivity detecting unit 3 for receiving the actual radioactivity intensity value a detected by the radioactivity detecting unit 3_iThe first data processing module is further electrically connected with the user interaction unit 5, and is configured to receive the simulated three-dimensional radioactive response distribution data, which is transmitted by the user interaction unit 5 and is not leaked, and calculate a normal radioactive intensity value a of the detection point when no leakage occurs according to the simulated three-dimensional radioactive response distribution data when no leakage occurs_iOThen the actual radioactivity intensity value A is calculated_iIntensity value A of normal radioactivity_i0Making a comparison according to A_iAnd A_i0The comparison result of (2) determines whether or not the heat transfer tubes 2 in the steam generator 1 are leaking.

In particular, when the actual radioactivity intensity value A is_iGreater than normal radioactivity intensity value A_i0If so, determining that the heat transfer pipe 2 in the steam generator 1 leaks; otherwise, no leakage occurs in the heat transfer tubes 2 in the steam generator 1. The actual radioactivity intensity value A of the detection point by the radioactivity detection unit_i0Carrying out continuous detection, and continuously detecting the actual radioactivity intensity value A by the first data processing module_iIntensity value A of normal radioactivity_i0And comparing the temperature and the humidity so as to judge whether the heat transfer pipe 2 in the steam generator 1 leaks or not in real time and realize online monitoring. In practical operation, the actual radioactivity intensity value A can be processed according to a certain processing frequency according to actual conditions_iIntensity value A of normal radioactivity_i0The comparison is performed so that the amount of data processing can be greatly reduced.

Compared with the prior art, the system adopts the actual radioactivity intensity value A of the position of the detection point_iCarry out continuous detection to carry out data processing, thereby can carry out on-line monitoring to steam generator 1, whether the radioactivity leakage takes place for heat-transfer pipe 2 that can the rapid judgement steam generator 1, thereby make the staff in time overhaul heat-transfer pipe 2, ensure nuclear power plant operation safety.

In this embodiment, the data processing unit may be any terminal such as a computer having a logic program for running data processing. The detection point monitor is preferably a boron-coated counting tube or an ionization chamber, and can be selected according to the range of radioactivity intensity.

In some embodiments, the system further comprises a steam generator model and a simulation unit electrically connected to the user interaction unit for simulating a three-dimensional distribution of radioactive responses in the steam generator when no leak has occurred in the steam generator model to obtain simulated three-dimensional distribution data of radioactive responses when no leak has occurred and transmitting the data to the user interaction unit. In this embodiment, the simulation unit preferably uses a monte carlo program.

In some embodiments, the user interaction unit 5 further presets simulated three-dimensional distribution data of radioactive response during leakage to obtain simulated three-dimensional distribution of radioactive response during leakage, and transmits the simulated three-dimensional distribution data of radioactive response during leakage;

the data processing unit 4 further comprises a second data processing module, which is respectively electrically connected with the user interaction unit and the radioactivity detection unit, and is used for receiving the simulated three-dimensional distribution data of radioactivity response in the leakage, which is transmitted by the user interaction unit 5, and calculating a plurality of leakage radioactivity intensity values a corresponding to detection points in the leakage of the heat transfer tubes 2 at different positions in the steam generator 1 according to the simulated three-dimensional distribution data of radioactivity response in the leakage_jkThen the actual radioactivity intensity value A transmitted by the radioactivity detection unit_iWith respective leakage radioactivity intensity value A_jkMaking a comparison according to A_iAnd A_jkThe comparison of (a) locates the location where the leak occurred.

Where j denotes a predetermined location where a leak occurs, j is a positive integer, i.e., j is 1, 2, 3, and_jkindicating the radioactive response intensity at different positions k within the steam generator 1 at which a leak occurs at the j position. AIn general, the more the preset leakage position j is, and the more the position k of the simulated radioactive response intensity is selected in the steam generator 1 under the condition of the same preset leakage position j, the more the accuracy of the subsequent positioning of the leakage position is favorably improved. The actual radioactivity intensity value A_iLeakage radioactivity intensity value B corresponding to different positions k in the steam generator 1 when the heat transfer pipe 2 at different positions j leaks_jkComparing one by one when the actual radioactivity intensity value A_iEqual to the leak radioactivity intensity value B_jkWhen it is, then B_jkThe indicated position where the leakage is supposed to occur is the position where the leakage occurs. For example, B₂₃＝A_iIf so, the predetermined position where the leakage occurs, which is represented by j 2, is the position where the leakage occurs.

Considering that in actual operation, there may be a plurality of B_jkEqual to Ai, i.e. the radioactive response of the preset probing point to a plurality of preset leakage positions is the same, and at this time, the leakage position can be further determined by the field detection of workers and the like. For example, if B is present₂₃、B₆₇、B₈₉Are all equal to A_iIf there is a possibility that any of the preset leak positions represented by j 2, 6, and 8 is a leak position, the worker detects the heat transfer tubes 2 at the three positions j 2, 6, and 8 and further specifies the leak position.

In some embodiments, the user interaction unit further includes a display module for displaying the judgment result output by the first data processing module and the position of the leakage occurring output by the second data processing module.

Compared with the prior art, the system can position and display the position where leakage occurs, can improve the maintenance efficiency, and greatly reduces the maintenance time and the workload of maintenance personnel.

In some embodiments, the simulation unit is further configured to obtain a simulated three-dimensional distribution of the radioactive response in the steam generator 1 when the heat transfer tubes at different positions in the steam generator 1 simulated in the steam generator model have leaks, and send the simulated three-dimensional distribution of the radioactive response in the steam generator 1 to the user interaction unit.

In some embodiments, the system further comprises a storage unit (not shown in the figures) electrically connected to the radioactivity detecting unit 3 for storing the actual radioactivity intensity value a detected by the radioactivity detecting unit 3_iHistorical data of (a); the data processing unit further comprises a third data processing module for obtaining an actual radioactivity intensity value A detected by the radioactivity detecting unit 3_iAnd the storage unit is also electrically connected with the third data processing module and is used for storing the historical data of the actual radioactive response three-dimensional distribution.

Of course, the storage unit can also be electrically connected with the first data processing module and the second data processing module respectively for storing the actual radioactivity intensity value A_iIntensity value A of normal radioactivity_i0Historical data of the results of the comparison and storing the actual radioactivity intensity values A_iAnd leak radioactivity intensity value B_jkHistorical data of the results of the comparison.

In some embodiments, the system further comprises an alarm unit (not shown in the figures), the alarm unit is electrically connected with the data processing unit, the data processing unit is further configured to send an alarm control signal to the alarm unit when the steam generator is determined to have a leak, and the alarm unit is configured to send an alarm prompt (such as sending an alarm sound) according to the alarm signal sent by the data processing unit.

In some embodiments, the number of the radioactivity detecting units 3 may be one set, or may be multiple sets, and may be specifically adjusted according to actual needs. The detection point monitor of each set of radioactivity detection unit 3 is disposed at a position below the water level of the steam generator 1.

Specifically, when the number of the radioactivity detecting units 3 is plural, the detecting point monitors of the radioactivity detecting units 3 may be distributed inside the steam generator 1, outside the steam generator 1, or a part of the detecting point monitors may be arranged inside the steam generator 1 and another part of the detecting point monitors may be arranged outside the steam generator 1. By respectively arranging the radioactivity detecting units 3 at different positions, mutual verification can be performed between the results of monitoring and judging by the radioactivity detecting units at different positions, so that the judging accuracy is improved. When the number of the radioactivity detecting units 3 is one, the detecting point monitors of the radioactivity detecting units 3 may be distributed inside the steam generator 1 or outside the steam generator 1.

The monitoring system of the nuclear power plant steam generator of the embodiment can carry out on-line monitoring on the steam generator, can quickly judge whether the heat transfer pipe of the steam generator leaks by radioactivity, thereby enabling the working personnel to overhaul the heat transfer pipe in time, further solving the problem of radioactivity leakage by timely control, and improving the operation safety of the nuclear power plant. And furthermore, the position where leakage occurs can be positioned, the maintenance efficiency is improved, the maintenance time and the workload of maintenance personnel are greatly reduced, and the economic benefit of the nuclear power plant is improved.

It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.