CN108679355B - Method and device for dredging boron water pipeline in nuclear power plant - Google Patents

Abstract

Translated fromChinese

本申请涉及核电站冷却技术领域，尤其涉及一种疏通核电站硼水管路的方法，可应用于包括硼水管路系统的核电站中，该硼水管路系统包括相互贯通连接的多根管道，所述方法包括：当所述硼水管路系统因硼酸结晶而发生堵塞时，在所述多根管道中检测出发生堵塞的故障管道；对所述故障管道进行加热，以疏通所述故障管道。上述疏通核电站硼水管路的方法，通过对发生堵塞的管道进行加热，能够使得因诸如降温等而产生的堵塞结晶重新溶解至硼酸溶液中，从而无需进行割管或更换管道就能疏通管道，不仅方便易行，且耗时较少，不但能够使得发生堵塞的冷却回路能及时恢复正常，同时还能大大降低维护人员在疏通管道时所承受的照射剂量，且还不会产生放射性固定废物。

The present application relates to the technical field of nuclear power plant cooling, and in particular, to a method for dredging a boron water pipeline in a nuclear power plant, which can be applied to a nuclear power plant including a boron water pipeline system, where the boron water pipeline system includes a plurality of pipelines that are connected through each other, and the method includes: : When the boron water pipeline system is blocked due to boric acid crystallization, the blocked faulty pipeline is detected in the plurality of pipelines; the faulty pipeline is heated to clear the faulty pipeline. The above-mentioned method for dredging the boron water pipeline of a nuclear power plant, by heating the blocked pipeline, can re-dissolve the blocked crystals caused by cooling, etc. into the boric acid solution, so that the pipeline can be dredged without cutting or replacing the pipeline. It is convenient and easy to operate, and it takes less time. It can not only make the blocked cooling circuit return to normal in time, but also greatly reduce the irradiation dose for maintenance personnel when dredging the pipeline, and will not generate radioactive fixed waste.

Description

Method and device for dredging boron water pipeline of nuclear power station

Technical Field

The invention relates to the technical field of nuclear power station pipeline dredging, in particular to a method and a device for dredging a boron water pipeline of a nuclear power station.

Background

The boron water pipeline is an important component in the nuclear power plant, and the boron water pipeline is mainly used as a neutron moderator to perform auxiliary control on the operation of the nuclear power plant. The traditional boric acid solution is generally circulated through a plurality of through pipelines to avoid the crystallization of the boric acid. However, in the actual operation process, due to the change of the local environment temperature of the pipeline, boron in the boric acid solution can be caused to be crystallized along with the reduction of the environment temperature, and once the boric acid is crystallized, deposited and piled, the boric acid water pipeline can be blocked, so that the boric acid crystallization is aggravated, and even the boric acid water pipeline is completely blocked, so that the boric acid water pipeline cannot work normally, and the safe operation of the nuclear power station is seriously influenced.

At present, when a boric acid crystal blockage fault occurs in a boron water pipeline of a nuclear power station, the boric acid crystal blockage fault is generally discharged by adopting a method of cutting a pipe or replacing the pipeline. However, the cutting or replacement of the pipes takes a long time, which not only makes the cooling circuit unusable for a long time, but also exposes the maintenance personnel to a large dose of radiation, while also generating a large amount of radioactive fixed waste, such as pipe waste, crystals causing blockages, etc.

Disclosure of Invention

Therefore, it is necessary to provide a method and a device for dredging a boron water pipeline of a nuclear power station aiming at the above technical problems, so that when the boron water pipeline is blocked by boric acid crystallization, the blocked boron water pipeline can be dredged without cutting or replacing the pipeline, the consumed time is short, the blocked boron water pipeline can be recovered to be normal in time, meanwhile, the irradiation dose born by maintenance personnel during dredging the pipeline is greatly reduced, and the radioactive fixed waste cannot be generated while faults are eliminated.

A method for dredging boron water pipelines of a nuclear power station, which can be applied to the nuclear power station, wherein the nuclear power station comprises a boron water pipeline system, the boron water pipeline system comprises a plurality of pipelines which are communicated and connected with each other, and the method comprises the following steps:

when the boron water pipeline system is blocked due to the crystallization of boric acid, detecting a blocked fault pipeline in the plurality of pipelines;

heating the faulty conduit to unblock the faulty conduit.

According to the method for dredging the boron water pipeline of the nuclear power station, the pipeline which is blocked is heated, so that the blocking crystals precipitated due to temperature reduction and the like are dissolved into the boric acid solution again, the pipeline can be dredged without cutting or replacing the pipeline, the method is not only convenient and easy to implement, but also consumes less time, the cooling loop which is blocked can be recovered to be normal in time, meanwhile, the irradiation dose born by maintenance personnel during dredging the pipeline can be greatly reduced, and radioactive fixed wastes cannot be generated.

In an alternative embodiment, ultrasonic waves are used in the plurality of conduits to detect a blocked faulty conduit.

In an optional embodiment, the method further comprises:

detecting a blocked area in the faulty pipeline by using ultrasonic waves;

wherein the faulty conduit is heated within the plugged region.

In an alternative embodiment, the faulty conduit is heated using a heating tape.

In an optional embodiment, the method further comprises:

and judging whether the boron water pipeline system is blocked or not by detecting the temperature of the boric acid solution in the boron water pipeline system.

In an optional embodiment, the method further comprises:

sampling or simulating sample preparation is carried out on the boric acid solution in the fault pipeline to obtain the dissolution temperature of the boric acid crystal;

wherein the temperature at which the faulty conduit is heated is greater than or equal to the dissolution temperature.

In an alternative embodiment, the failed conduit is pressurized with water to unblock the failed conduit while the failed conduit is heated.

In another optional embodiment of the present application, a device for dredging a boron water pipeline of a nuclear power plant is further provided, which may be applied to a nuclear power plant, where the nuclear power plant includes a boron water pipeline system, the boron water pipeline system includes a plurality of pipelines interconnected through each other, and the device may include:

a detector for detecting a faulty pipe, in which a blockage occurs, and a blocked area in the faulty pipe from among the plurality of pipes;

the heater is arranged on the outer walls of the pipelines;

a controller connected to the detector and the heater, respectively;

the controller is used for controlling a heater arranged outside the blocked area to heat according to the faulty pipeline detected by the detector and the blocked area in the faulty pipeline so as to dredge the faulty pipeline.

According to the device for dredging the boron water pipeline of the nuclear power station, the parameters such as the blocked fault pipeline and the blocked area range, shape, size and the like in the fault pipeline can be accurately detected by using the detector; the controller then can be according to above-mentioned parameter, block up the region through controlling corresponding heater in to the trouble pipeline and carry out accurate, quick heating, thereby can make because of such as cooling etc. and the jam crystallization that appears can be quick dissolve to the boric acid solution again, need not to cut the pipe or change the pipeline promptly and just can dredge the prerequisite of pipeline under, make the cooling circuit that takes place to block up in time resume normally, not only convenient easy and consuming time less, simultaneously can also greatly reduced maintainer irradiation dose that bears when dredging the pipeline, and can not produce the incidental adverse effect such as the fixed waste of radioactivity yet.

In an alternative embodiment, the apparatus may further comprise:

the temperature sensor is arranged in the pipeline and used for measuring the temperature of the boric acid solution in the pipeline;

the controller is connected with the temperature sensor and used for judging whether the boron water pipeline system is blocked or not according to the flow rate measured by the temperature sensor; and

and triggering the detector to work when the blockage in the boron water pipeline system is determined.

In an alternative embodiment, the apparatus may further comprise:

the water injector is arranged at the through connection position between the adjacent pipelines;

the controller is connected with the water injector and used for triggering the water injector to fill water in the fault pipeline at high pressure.

Drawings

FIG. 1 is a flow diagram of a method for unblocking a boron water line of a nuclear power plant in one embodiment;

FIG. 2 is a schematic structural diagram of a device for dredging boron water pipelines of a nuclear power plant in one embodiment;

fig. 3 is a flow chart of a method for dredging a boron water pipeline of a nuclear power plant in combination with fig. 1 and 2 in one embodiment.

Detailed Description

In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.

At present, in a boron water pipeline system of a nuclear power plant such as a pressurized water reactor, a plurality of long pipelines are generally adopted to form a circulating pipeline, so that the operation of the nuclear power plant is assisted and controlled by introducing a boric acid solution and the like serving as a neutron moderator into the pipelines. However, the boric acid solution can generate boric acid crystallization along with the reduction of the environmental temperature, and the crystallization can block the pipeline through deposition and accumulation, so that the operation of a boron water pipeline system is influenced, even a single row of boron water pipelines can not work when the blockage is serious, the traditional method can only stop the row of boron water pipelines, and solve the problem of pipeline blockage through pipe cutting or pipeline replacement. Specifically, the method comprises the following steps:

FIG. 1 is a flow chart of a method for dredging a boron water pipeline of a nuclear power plant in one embodiment. In an alternative embodiment, as shown in fig. 1, a method for dredging boron water pipelines of a nuclear power plant can be applied to a nuclear power plant including a boron water pipeline system, and the boron water pipeline system can include a plurality of pipelines which are communicated with each other, and the method can include the following steps:

and step S11, when the boron water pipeline system is blocked, detecting the blocked fault pipeline.

For example, after a boron water piping system is detected to be clogged, each pipe can be inspected using ultrasonic waves to determine the malfunctioning pipe that is clogged. Wherein, the fault pipeline can be one or more, and one or more parts in the same pipeline can be blocked.

And step S12, heating the fault pipeline to dredge the fault pipeline.

For example, after the detection determines that the blocked faulty pipeline occurs, the faulty pipeline may be heated by, for example, a heating belt or other similar means, so as to increase the temperature of the environment in which the boric acid solution in the faulty pipeline is located, and since the solubility of the solute boron in the boric acid solution increases with the increase of the temperature, the boric acid crystals may be encouraged to re-dissolve into the boric acid solution, so as to reduce the crystals causing the blockage, thereby achieving the purpose of dredging the faulty pipeline.

In another optional embodiment, while the faulty pipe is detected, the faulty pipe may be detected by using ultrasonic waves, for example, to acquire parameters of a position, an area range, a size, a shape, and the like of a blockage in the current faulty pipe, and of course, the parameters of the blockage may also be synchronously acquired while the faulty pipe is detected, which may be specifically set according to an actual situation, and the embodiment of the present application is not limited thereto. Follow-up still can be according to the parameter of the jam of above-mentioned collection, block up the regional heating strategy that carries out the correspondence in the pipeline to the trouble, can only heat to the jam region of trouble pipeline even, and other not blocked regions do not do the heating operation, and then when high-efficient mediation is blockked up, can also promote the energy consumption efficiency of heating.

In an alternative embodiment, while the above-mentioned heating method is used to dissolve the blockage in the faulty conduit, the dissolution of the blockage (such as boric acid crystallization, etc.) can be accelerated by pressurizing and filling water into the faulty conduit (i.e. water is used as a solvent of the solution, and when the solvent is other substances, the water can be replaced by the corresponding solvent), so as to further increase the speed of dredging the blockage of the faulty conduit.

In another optional embodiment, after the faulty pipelines are detected, the dissolution temperature of the boric acid crystals at the blockage position in each faulty pipeline can be obtained by sampling or simulating sample preparation and the like of the boric acid solution in the faulty pipeline, and then the heating temperature of the corresponding faulty pipeline can be kept above the obtained dissolution temperature all the time, so that the blockage dredging efficiency is improved, and meanwhile, the temperature of the pipeline can be kept in the temperature range capable of dissolving the blockage all the time through subsequent heating. Wherein, parameters which can cause the change of the solute solubility, such as the environmental temperature, the hydraulic pressure in the pipeline, and the like, can be comprehensively considered when the sample preparation is simulated. Of course, the dissolution temperatures of different boric acid crystals can be obtained based on multiple test data, and the solution temperature threshold of the boric acid crystals can be obtained through big data analysis, and then the heating temperature can be directly maintained within the range of the solution temperature threshold when the blockage is detected, or the heating temperature is higher than the solution temperature threshold for heating, so as to dredge the fault pipeline.

In one optional embodiment, whether the boron water pipeline system is blocked can be judged by detecting the temperature of the boric acid solution in the boron water pipeline system in real time. For example, a temperature threshold can be determined according to experience or big data analysis, when the temperature in the boron water pipeline system is detected to be less than the temperature threshold, an alarm of blockage of the boron water pipeline system is triggered, and the blockage can be unblocked by adopting the method.

It should be noted that "clogging" in the embodiments of the present application means that the temperature of the boric acid solution in the local pipe is lowered due to the deposition of solid matter in the boron water piping system. In addition, whether the boron water pipeline system is blocked or not can be judged based on the flowing speed of the boric acid solution in the pipeline or other parameters.

FIG. 2 is a schematic structural diagram of a device for dredging boron water pipelines of a nuclear power plant in one embodiment. As shown in fig. 2, an apparatus 1 for dredging a boron water pipeline of a nuclear power plant, which may be applied to dredging apipeline 2 in a boron water pipeline system of a nuclear power plant by using the method for dredging a boron water pipeline of a nuclear power plant in the foregoing embodiment, may include acontroller 12, adetector 13 and aheater 14, that is, thecontroller 12 is connected to thedetector 13 and theheater 14, respectively, and thedetector 13 may be an ultrasonic detector, and thedetector 13 may be disposed adjacent to thepipeline 12; theheater 14 may be disposed on the outer wall of theduct 2; wherein, can all set up one or more heater on the outer wall of every pipeline, when being provided with a plurality of heaters on the same root pipeline, this a plurality of heaters can carry out differentiation formula heating to this different regions of pipeline promptly. Correspondingly, when the boron water pipeline system is blocked, thecontroller 12 can detect thepipeline 2 in the boron water pipeline system by using thedetector 13 to determine the pipeline (namely, the fault pipeline) 2 which is blocked, and then thecontroller 12 can control theheater 14 to heat the corresponding pipeline (namely, the fault pipeline) 2 according to the information fed back by thedetector 13, so that the blockage boric acid crystal in thepipeline 2 is dissolved into the boric acid solution again, and the effect of dredging the fault pipeline is achieved.

As shown in fig. 2, in an alternative embodiment, thedetector 13 can detect the faulty pipes and also detect parameters such as the position, shape, size, and area range of the blocked area in each faulty pipe; accordingly, thecontroller 12 may control theheater 14 to perform a particular heating strategy for the failed conduit or the blocked region of the failed conduit according to the parameters of the blocked region as described above. For example, the heating strategy can be set according to the heating temperature, the heating temperature increasing speed, the holding temperature, the heating range and the like, so as to further improve the dredging rate and the energy consumption efficiency of thepipeline 12.

In an alternative embodiment, as shown in fig. 2, the device 1 for dredging a boron water pipeline in a nuclear power plant may further include atemperature sensor 11, thetemperature sensor 11 may be disposed in an outer wall or an inner wall of apipeline 12 of the boron water pipeline system, and thetemperature sensor 11 is further connected to thecontroller 12, that is, thecontroller 12 may compare a reference temperature threshold value built in the controller with a current temperature measured by thetemperature sensor 11 in real time to determine whether a blockage fault occurs in the boron water pipeline system, and may trigger thedetector 13 to start operating after the blockage fault is determined. The number of thetemperature sensors 11 may be multiple, and each pipeline may be provided with onetemperature sensor 11, and as long as the temperature measured by one of thetemperature sensors 11 is less than the reference temperature threshold, it may be determined that the boron water pipeline system is blocked. Of course, in other embodiments, the determination of the blockage failure of the boron water pipeline system may be performed by other methods, for example, a device and a method for determining the blockage failure based on the flow rate of the boric acid solution, the hydraulic pressure of the boric acid solution, and the like.

In another alternative embodiment, as shown in fig. 2, the device for dredging a boron water pipeline of a nuclear power plant may further include awater injector 15, where thewater injector 15 is connected to thecontroller 12, so as to control thewater injector 15 to pressurize and fill water in the faulty pipeline while theheater 14 heats the faulty pipeline, and the pressure of the pressurized and filled water may be specifically set according to the pressure-bearing capacity of the faulty pipeline and the shape, size, etc. of the blockage, that is, the pressure of the pressurized and filled water is within the pressure-bearing range of the faulty pipeline, and an appropriate water pressure is selected to increase the dissolution rate of the blockage. The number of thewater injectors 15 may be multiple, that is, onewater injector 15 may be disposed at the joint of different pipelines, or amovable water injector 15 may be used to fill water at high pressure to a corresponding faulty pipeline as required.

Fig. 3 is a flow chart of a method for dredging a boron water pipeline of a nuclear power plant in combination with fig. 1 and 2 in one embodiment.

The following description will be made in detail by taking a pressurized water reactor nuclear power station as an example and using a boric acid solution as a neutron moderator, with reference to the accompanying drawings 1 to 3:

the concentration of boron in the boric acid solution used as the neutron moderator is generally 2400-7700 ppm, crystals can be precipitated when the concentration of boron is greater than 10000ppm in a room temperature environment, and the concentration of the precipitated crystals can be gradually reduced when the environment temperature changes, namely, the boric acid solution with the concentration of 2400-7700 ppm is adopted, boric acid crystals can appear when the environment temperature is reduced, and further a boric water circulation pipeline can be blocked.

As shown in FIGS. 1 to 3, the method for dredging the boron water pipeline of the nuclear power station can comprise the following steps:

and step S21, acquiring the temperature of the boric acid solution in the pipeline in real time.

Specifically, thetemperature sensor 11 may be used to acquire the temperature of the boric acid solution in real time.

And step S22, judging whether the boron water pipeline system is blocked. And if the boron water pipeline system is blocked, continuing to step S23, otherwise, continuing to step S21.

Specifically, thecontroller 12 may be utilized to determine whether the temperature of the collected boric acid solution in the pipeline is greater than a preset temperature threshold; if the temperature of the collected boric acid solution in the pipeline is less than or equal to the preset temperature threshold value, which indicates that the boron water pipeline system is blocked, the step S23 can be continued; and if the temperature of the collected boric acid solution in the pipeline is greater than the preset temperature threshold value, the boric acid solution in the pipeline is indicated to be free from blockage, namely, the boric acid solution works normally, and the step S21 can be continued after the preset time period, so that the circulating detection of the temperature is realized, and the purpose of real-time monitoring is achieved.

In step S23, a faulty pipe and a blocked area in the faulty pipe are detected.

Specifically, after it is determined that a blockage fault occurs in the boron water pipeline system, thedetector 13 is used for detecting the pipeline of the boron water pipeline system to determine the blocked fault pipeline, collect parameters such as a blocked area and a blocked range in the fault pipeline, and also collect parameters such as a shape and a size of a blockage.

And step S24, heating the blocked area and pressurizing and filling the fault pipeline with water.

Specifically, thecontroller 12 controls theheater 14 to correspondingly heat the blocked area of the faulty pipeline according to the parameters collected by thedetector 13, and controls thewater injector 15 to pressurize and fill the faulty pipeline, so as to rapidly, efficiently and safely dredge the faulty pipeline.

In an alternative embodiment, the dissolution temperature of the boric acid crystals in the faulty pipeline can be determined by sampling or simulating the sample preparation of the boric acid solution in the faulty pipeline and performing experiments in a laboratory, and then the heating operation of theheater 14 can be controlled according to the dissolution temperature, so as to further improve the energy efficiency and efficiency of dredging the blockage.

For example: first, in the case of a pipeline blockage in a boron recovery system (TEP), the dissolution temperature of boric acid crystals in a faulty pipeline can be determined to be 60 degrees by simulation sample preparation and experiment. It should be noted that, because there are differences in parameters such as hydraulic pressure, concentration, etc. at different pipelines or different positions of the same pipeline, so that there is a certain difference in the solution temperature of boric acid crystals at various places, specific simulation sample preparation and test can be performed for different faulty pipelines to determine the dissolution temperature of boric acid crystals in the faulty pipeline.

Secondly, ultrasonic detection (UT) degree fault pipelines are adopted for detection to determine parameters such as the range, the boundary and the like of the blockage, for example, the length of the blockage is 45 meters, and the blockage comprises a 30-meter-long tubular heat exchanger.

Then, winding a line heater (namely a heat tracing band) with the heating temperature of 60-100 ℃ around the blocked area of the fault pipeline (the heat tracing band can be arranged on each pipeline in advance), wherein the line heater has the heat preservation function and can automatically cut off the power when the temperature exceeds 105 ℃; wherein the wire heater wound on the blocked area of the faulty pipe has a length of approximately 100 meters.

Then, after the line heater is powered on, the temperature on the fault pipeline is monitored in real time, and when the temperature rise on the fault pipeline is slow, a heat preservation film (such as fireproof cloth) can be wound outside the line heater, so that the heat generated by the line heater can be applied to the fault pipeline as much as possible; for example, heating by the above-described wire heater for 8 hours causes the temperature on the faulty pipe to rise to 75 degrees.

Meanwhile, when the wire heater is used for heating, the pressurizing and water filling can be carried out at one end of the fault pipeline through the water injector so as to ensure that the boron crystal has enough water solution to carry out solution, and in order to improve the heating effect, the pressurizing and water filling operation can be carried out by adopting hot water with the temperature of more than 60 ℃; of course, when the dissolution temperature is higher, the water temperature of the pressurized water filling can be selected to be proper according to specific requirements and the bearing capacity of equipment.

In the implementation, practical operation shows that the pipeline can be dredged after heating and maintaining 75 ℃ for 3 days aiming at the blockage with the TEP45 m length, and the traditional method for dredging by heating adopts about 15 days for pipe cutting or pipe replacement, namely the method for dredging by heating can greatly save the time for removing faults. Meanwhile, 30-50 ten thousand RMB are consumed by cutting the pipe or replacing the pipeline, and only more than 1000 RMB are needed by adopting the method in the application for estimation, so that the cost of discharging the blockage can be greatly saved.

The technical features of the embodiments described above may be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the embodiments described above are not described, but should be considered as being within the scope of the present specification as long as there is no contradiction between the combinations of the technical features.

The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.

Claims (10)

Translated fromChinese

1.一种疏通核电站硼水管路的方法，应用于核电站中，所述核电站包括硼水管路系统，所述硼水管路系统包括相互贯通连接的多根管道，其特征在于，所述方法包括：1. a method for dredging a boron water pipeline of a nuclear power plant, applied in the nuclear power plant, the nuclear power plant comprises a boron water pipeline system, and the boron water pipeline system comprises a plurality of pipelines that are connected through each other, it is characterized in that, the method comprises:通过检测所述硼水管路系统中硼酸溶液的温度，来判断所述硼水管路系统是否发生堵塞；Determine whether the boron water pipeline system is blocked by detecting the temperature of the boric acid solution in the boron water pipeline system;当所述硼水管路系统因硼酸结晶而发生堵塞时，基于超声波在所述多根管道中检测出发生堵塞的故障管道，并采集所述故障管道中堵塞物的位置、区域、形状及尺寸；When the boron water pipeline system is blocked due to boric acid crystallization, detecting the blocked faulty pipeline in the plurality of pipelines based on ultrasonic waves, and collecting the position, area, shape and size of the blockage in the faulty pipeline;对所述故障管道进行加热，以疏通所述故障管道；heating the faulty pipeline to unblock the faulty pipeline;在对所述故障管道进行加热的同时，对该故障管道进行加压充水，以疏通所述故障管道，该加压充水的压强基于所述故障管道的承压能力及堵塞物的形状、尺寸而设定。While heating the faulty pipeline, pressurize the faulty pipeline with water to dredge the faulty pipeline. The pressure of the pressurized water is based on the pressure-bearing capacity of the faulty pipeline and the shape of the blockage, size is set.2.如权利要求1所述的方法，其特征在于，所述方法还包括：2. The method of claim 1, wherein the method further comprises:对所述故障管道内的硼酸溶液进行模拟配样来获取所述硼酸结晶的溶解温度；Simulate sample preparation for the boric acid solution in the faulty pipeline to obtain the dissolution temperature of the boric acid crystal;其中，对所述故障管道进行加热的温度大于或等于所述溶解温度。Wherein, the temperature for heating the faulty pipeline is greater than or equal to the dissolution temperature.3.如权利要求1所述的方法，其特征在于，所述方法还包括：3. The method of claim 1, wherein the method further comprises:采用超声波检测出所述故障管道中堵塞区域；Use ultrasonic to detect the blocked area in the faulty pipeline;其中，在所述堵塞区域内对所述故障管道进行加热。wherein the faulty pipe is heated in the blocked region.4.如权利要求1所述的方法，其特征在于，采用加热带对所述故障管道进行加热。4. The method of claim 1, wherein the faulty pipe is heated using a heating tape.5.如权利要求1所述的方法，其特征在于，所述方法还包括：5. The method of claim 1, wherein the method further comprises:对所述故障管道内的硼酸溶液进行采样来获取所述硼酸结晶的溶解温度；sampling the boric acid solution in the faulty pipeline to obtain the dissolution temperature of the boric acid crystal;其中，对所述故障管道进行加热的温度大于或等于所述溶解温度。Wherein, the temperature for heating the faulty pipeline is greater than or equal to the dissolution temperature.6.一种疏通核电站硼水管路的装置，应用于核电站中，所述核电站包括硼水管路系统，所述硼水管路系统包括相互贯通连接的多根管道，其特征在于，所述装置包括：6. A device for dredging a boron water pipeline of a nuclear power plant, applied in a nuclear power plant, wherein the nuclear power plant comprises a boron water pipeline system, and the boron water pipeline system comprises a plurality of pipes connected through each other, wherein the device comprises:检测器，用于基于超声波从所述多根管道中检测出发生堵塞的故障管道和所述故障管道中堵塞物的形状、尺寸、位置及区域；a detector for detecting, from the plurality of pipes, a blocked faulty pipe and the shape, size, position and area of the blockage in the faulty pipe based on ultrasonic waves;加热器，设置于所述多根管道的外壁上；a heater, arranged on the outer walls of the plurality of pipes;注水器，设置在相邻管道之间的贯通连接处；控制器，分别与所述检测器、所述加热器和所述注水器连接；A water injector is arranged at the through connection between adjacent pipes; a controller is connected to the detector, the heater and the water injector respectively;温度传感器，设置于所述管道中，用于测量所述管道中硼酸溶液的温度；a temperature sensor, arranged in the pipeline, for measuring the temperature of the boric acid solution in the pipeline;其中，所述控制器用于根据所述检测器所检测到的所述故障管道和该故障管道中的堵塞区域，控制对应的加热器进行加热，以疏通所述故障管道，所述控制器用于触发所述注水器对所述故障管道内进行高压冲水，该高压冲水的压强基于所述故障管道的承压能力及堵塞物的形状、尺寸而设定；所述控制器与所述温度传感器连接，用于根据所述温度传感器所测量的温度判断所述硼水管路系统中是否发生堵塞；以及Wherein, the controller is used to control the corresponding heater to heat according to the faulty pipeline detected by the detector and the blocked area in the faulty pipeline, so as to unblock the faulty pipeline, and the controller is used to trigger The water injector performs high-pressure flushing in the faulty pipeline, and the pressure of the high-pressure flushing water is set based on the pressure-bearing capacity of the faulty pipeline and the shape and size of the blockage; the controller and the temperature sensor connected for judging whether blockage occurs in the boron water pipeline system according to the temperature measured by the temperature sensor; and在确定所述硼水管路系统中发生堵塞时，触发所述检测器进行工作。When it is determined that blockage occurs in the boron water pipeline system, the detector is triggered to work.7.如权利要求6所述的装置，其特征在于，每根所述管道中均设置有一个所述温度传感器。7. The device of claim 6, wherein each of the pipes is provided with one of the temperature sensors.8.如权利要求6所述的装置，其特征在于，所述温度传感器位于所述管道的外壁中。8. The apparatus of claim 6, wherein the temperature sensor is located in the outer wall of the conduit.9.如权利要求6所述的装置，其特征在于，所述温度传感器位于所述管道的内壁中。9. The apparatus of claim 6, wherein the temperature sensor is located in the inner wall of the conduit.10.如权利要求6所述的装置，其特征在于，所述注水器的数量为多个。10. The device of claim 6, wherein the number of the water injectors is plural.

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