Online measurement system for uranium content in waste liquid

Abstract

The invention provides a waste liquid uranium content on-line measurement system, which comprises an on-line sample introduction system, a detection system, an automatic control system and a DCS system, the on-line sample introduction system comprises a sample introduction pipeline, a sample introduction pump, an automatic dilution device and a flow cell, one end of the sample introduction pipeline is connected with a waste liquid sampling port, the other end of the sample introduction pipeline is connected with the automatic dilution device, and the flow cell is connected with the detection system. The automatic diluting device is connected with the flow cell; the detection system comprises a graphite crystal pre-diffraction XRF measurement system, the graphite crystal pre-diffraction XRF measurement system corresponds to the flow cell, the graphite crystal pre-diffraction XRF measurement system is electrically connected with the automatic control system, and the automatic control system is electrically connected with the DCS. According to the online measurement system for the uranium content of the waste liquid, online measurement of the uranium content of the waste liquid of different source items such as a hydrofluoric acid-containing uranium-containing system, a nitric acid-containing uranium-containing system and a carbonate-containing uranium-containing system in a uranium purification and conversion production line can be realized, the detection time is shortened, and the automation level of an analysis and measurement technology is improved.

Description

Technical Field

[0001] The invention relates to the technical field of measuring uranium-containing waste liquid, in particular to an online measuring system for uranium content in waste liquid. Background Art

[0002] The nuclear chemical uranium purification and conversion production line has strict restrictions on environmental protection while operating stably. Therefore, the treatment of waste liquid generated during operation is crucial, and the uranium content in the treatment process is an essential analysis item, which reflects both the operating status and the operating results. Therefore, timely and accurate measurement of the uranium content in the waste liquid is of great significance to the safe production and environmental protection of uranium purification and conversion.

[0003] At present, through a large number of investigations, sorting, classification, sampling and analysis of the types and sources of uranium-containing waste liquid, it is found that the types and compositions of uranium-containing waste liquid in the production line are complex, and the uranium content in them also varies greatly. In the analysis and inspection, titration, burning weighing method and instrumental analysis methods were used for experiments. Through inspection, several relatively mature technologies have been determined, namely graphite crystal pre-diffraction XRF method, rapid uranium titration method, counting method (γ absorption method) and fluorescence method. Because the applicable media and concentration ranges of each method are different, a preliminary judgment of the sample is required before measurement, and the fluorescence method and titration method require pre-treatment of the sample. Sampling and detection practice shows that the sample analysis method based on graphite crystal pre-diffraction XRF technology is suitable for a wide range of acid and alkali media measurements. The measured uranium concentration range is (1-4000) mg / L, covering most of the uranium detection requirements in the waste liquid treatment process, and the relative error is controlled within 10%.

[0004] In actual operation, uranium detection is based on the offline detection results of sampling, and the detection cycle of a sample is 50 minutes. For the continuously running waste liquid treatment process, the timeliness is insufficient, especially when abnormal conditions occur, the treatment measures cannot be taken in time, which is extremely unfavorable to the stable operation and has a great impact on the further improvement of production efficiency. Summary of the invention

[0005] The object of the present invention is to provide an online measurement system for uranium content in waste liquid, which can realize online measurement of uranium content in waste liquid from different sources such as a hydrofluoric acid-containing uranium system, a nitric acid-containing uranium system, and a carbonate-containing uranium system in a uranium purification and conversion production line, shorten detection time, and improve the automation level of analysis and measurement technology.

[0006] The invention provides an online measurement system for uranium content in waste liquid, comprising an online sampling system, a detection system, an automatic control system and a DCS system. The online sampling system comprises a sampling pipeline, a sampling pump, an automatic diluting device and a circulation pool, one end of the sampling pipeline is connected to a sampling port of waste liquid, the other end of the sampling pipeline is connected to the automatic diluting device, and the automatic diluting device is connected to the circulation pool; the detection system comprises a graphite crystal pre-diffraction XRF measurement system, the graphite crystal pre-diffraction XRF measurement system corresponds to the circulation pool; the graphite crystal pre-diffraction XRF measurement system is electrically connected to the automatic control system, and the automatic control system is electrically connected to the DCS system.

[0007] According to the present invention, a system for online measurement of uranium content in waste liquid also includes a self-cleaning system, which includes a first cleaning pipeline, a second cleaning pipeline and a purge pipeline, wherein one end of the first cleaning pipeline is connected to a first cleaning liquid interface, and the other end of the first cleaning pipeline is connected to the injection pipeline; one end of the second cleaning pipeline is connected to a second cleaning liquid interface, and the other end of the second cleaning pipeline is connected to the automatic dilution device; one end of the purge pipeline is connected to a purge gas interface, and the other end of the purge pipeline is connected to the injection pipeline.

[0008] According to an online measurement system for uranium content in waste liquid provided by the present invention, a first control valve is provided on the first cleaning pipeline, a second control valve is provided on the second cleaning pipeline, and a third control valve is provided on the purge pipeline, and the first control valve, the second control valve and the third control valve are electrically connected to the automatic control system respectively.

[0009] According to the online measurement system for uranium content in waste liquid provided by the present invention, the self-cleaning system also includes a pure water pipeline, one end of the pure water pipeline is connected to the pure water interface, and the other end of the pure water pipeline is connected to the second cleaning pipeline.

[0010] According to the online measurement system for uranium content in waste liquid provided by the present invention, a fourth control valve is provided on the pure water pipeline, and the fourth control valve is electrically connected to the automatic control system.

[0011] According to the on-line measurement system for uranium content in waste liquid provided by the present invention, a cleaning liquid pump is also provided on the second cleaning pipeline.

[0012] According to an online measurement system for uranium content in waste liquid provided by the present invention, a pressure reducing valve, a quantitative valve and a fifth control valve are respectively provided on the sampling pipeline, and the pressure reducing valve, the quantitative valve and the fifth control valve are respectively electrically connected to the automatic control system.

[0013] According to an online measurement system for uranium content in waste liquid provided by the present invention, the outlet of the automatic dilution device is connected to the upper inlet of the circulation pool through a dilution liquid pipeline, a sixth control valve is provided on the dilution liquid pipeline, and the sixth control valve is electrically connected to the automatic control system.

[0014] According to an online measurement system for uranium content in waste liquid provided by the present invention, the lower outlet of the circulation pool is connected to a reflux pipe, a seventh control valve is provided on the reflux pipe, and the seventh control valve is electrically connected to the automatic control system.

[0015] According to the present invention, an online measurement system for uranium content in waste liquid also includes an exhaust duct, one end of which is connected to the reflux duct, and the other end of which is connected to an exhaust port; an eighth control valve is provided on the exhaust duct, and the eighth control valve is electrically connected to the automatic control system.

[0016] The invention provides an online measurement system for uranium content in waste liquid. The online sampling system, a detection system and an automatic control system are provided. The online sampling system comprises a sampling pipeline, a sampling pump, an automatic diluting device and a circulation pool. One end of the sampling pipeline is connected to a sampling port of waste liquid, the other end of the sampling pipeline is connected to the automatic diluting device, and the automatic diluting device is connected to the circulation pool. The online sampling system is used to allow waste liquid to smoothly enter the sampling pipeline through the waste liquid sampling port, and then flow through the automatic diluting device to quantitatively dilute the waste liquid, and then enter the circulation pool for subsequent quantitative analysis of waste liquid samples. The detection system comprises a graphite crystal pre-diffraction XRF measurement system, the graphite crystal pre-diffraction XRF measurement system corresponds to the circulation pool, the graphite crystal pre-diffraction XRF measurement system is electrically connected to the automatic control system, and the automatic control system is electrically connected to a DCS system. That is, the uranium content in the waste liquid stored in the circulation pool can be measured online through the graphite crystal pre-diffraction XRF measurement system, the automatic control system is used to automatically control the online measurement process of the online measurement system, and the measurement data is connected to the DCS system to realize real-time data transmission.

[0017] Therefore, the online measurement system for uranium content in waste liquid provided by the present invention can realize online sampling and detection during the operation of the waste liquid treatment process, can intuitively reflect the change trend of the single-point uranium content, shorten the detection time, improve the automation level of the analysis and measurement technology, realize the online and accurate monitoring of the uranium content in the waste liquid of the uranium purification and conversion production line, provide a technical basis for improving the waste liquid treatment of the uranium purification and conversion production line, can provide effective guidance and reliable support for the process operation, and provide strong technical support for environmental protection.

[0018] The system for online measurement of uranium content in waste liquid provided by the present invention can realize online measurement of uranium content in waste liquid from different sources such as a hydrofluoric acid-containing uranium system, a nitric acid-containing uranium system, and a carbonate-containing uranium system in a uranium purification and conversion production line, and has the significant advantages of a wide measurement range and a small relative error. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] In order to more clearly illustrate the specific implementation methods of the present invention or the technical solutions in the prior art, the drawings required for use in the specific implementation methods or the description of the prior art will be briefly introduced below. Obviously, the drawings described below are some implementation methods of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0020] Figure 1 The figure is a schematic diagram of the structure of the online measurement system for uranium content in waste liquid according to the present invention.

[0021] Figure 2 It is a schematic diagram of the structure of a single circulation cell in the online measurement system of uranium content in waste liquid of the present invention;

[0022] Figure 3 The figure is a schematic diagram of the arrangement of six circulation cells in the online measurement system for uranium content in waste liquid according to the present invention.

[0023] Description of reference numerals:

[0024] 1. Injection pipeline; 2. Injection pump; 3. Automatic dilution device; 4. Circulation cell; 5. Graphite crystal pre-diffraction XRF measurement system; 6. Automatic control system; 7. DCS system; 8. First cleaning pipeline; 9. Second cleaning pipeline; 10. Purge pipeline; 11. First control valve; 12. Second control valve; 13. Third control valve; 14. Pure water pipeline; 15. Fourth control valve; 16. Collimation channel; 17. X-ray tube; 18. Filter; 19. Detector; 20. Graphite crystal; 21. Pressure reducing valve; 22. Dosing valve; 23. Fifth control valve; 24. Sixth control valve; 25. Seventh control valve; 26. Reflux pipeline; 27. Exhaust pipeline; 28. Eighth control valve; 29. ​​Turntable. DETAILED DESCRIPTION

[0025] The technical solution of the present invention will be clearly and completely described below in conjunction with the embodiments. Obviously, the described embodiments are part of the embodiments of the present invention, rather than all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0026] In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inside", "outside", "clockwise", "counterclockwise" and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the accompanying drawings, and are only for the convenience of describing the present invention and simplifying the description, and do not indicate or imply that the referred device or element must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be understood as limiting the present invention.

[0027] In addition, the terms "first" and "second" are only used for descriptive purposes and cannot be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Therefore, the features defined as "first" and "second" may explicitly or implicitly include one or more of the features. In the description of the present invention, "multiple" means two or more, unless otherwise clearly and specifically defined. In addition, the terms "installed", "connected" and "connected" should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection, or it can be indirectly connected through an intermediate medium, or it can be the internal connection of two components. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0028] like Figures 1 to 3 As shown, the online measurement system for uranium content in waste liquid according to an embodiment of the present invention includes an online sampling system, a detection system, an automatic control system and a DCS system.

[0029] The online sampling system includes a sampling pipeline 1, a sampling pump 2, an automatic diluting device 3 and a circulation pool 4. One end of the sampling pipeline 1 is connected to the sampling port of the waste liquid, and the other end of the sampling pipeline 1 is connected to the automatic diluting device 3, and the automatic diluting device 3 is connected to the circulation pool 4. The function of the online sampling system is to allow the waste liquid to smoothly enter the sampling pipeline 1 through the waste liquid sampling port, and then flow through the automatic diluting device 3 to quantitatively dilute the waste liquid, and then enter the circulation pool 4, so as to facilitate the subsequent quantitative analysis of the waste liquid sample.

[0030] The detection system includes a graphite crystal pre-diffraction XRF measurement system 5, which corresponds to the circulation pool 4, and is electrically connected to an automatic control system 6, which is electrically connected to a DCS system 7. The graphite crystal pre-diffraction XRF measurement system 5 can measure the uranium content in the waste liquid stored in the circulation pool 4 online, and the automatic control system 6 is used to automatically control the online measurement process of the online measurement system, and the measurement data is connected to the DCS system 7 to realize real-time transmission of the measurement data.

[0031] Therefore, the online measurement system for uranium content in waste liquid of the embodiment of the present invention can realize online sampling and detection during the operation of the waste liquid treatment process, can intuitively reflect the change trend of the single-point uranium content, shorten the detection time, improve the automation level of the analysis and measurement technology, realize the online and accurate monitoring of the uranium content in the waste liquid of the uranium purification and conversion production line, provide a technical basis for improving the waste liquid treatment of the uranium purification and conversion production line, can provide effective guidance and reliable support for the process operation, and provide strong technical support for environmental protection.

[0032] The online measurement system for uranium content in waste liquid according to the embodiment of the present invention can realize online measurement of uranium content in waste liquid from different sources such as a hydrofluoric acid-containing uranium system, a nitric acid-containing uranium system, and a carbonate-containing uranium system in a uranium purification and conversion production line, and has the significant advantages of a wide measurement range and a small relative error.

[0033] The online measurement system for uranium content in waste liquid according to the embodiment of the present invention has excellent acid resistance, alkali resistance and corrosion resistance.

[0034] Specifically, the automatic dilution device 3 is mainly used for quantitative dilution of high-content (4000mg / L-8000mg / L) uranium-containing waste liquid. The sample enters the automatic dilution device 3 at a certain flow rate, and the sample is quantitatively diluted and then measured, which can realize online and accurate measurement of the uranium content of the waste liquid.

[0035] In some embodiments of the present invention, the system for online measurement of uranium content in waste liquid further includes a self-cleaning system, which includes a first cleaning pipeline 8, a second cleaning pipeline 9 and a purge pipeline 10, one end of the first cleaning pipeline 8 is connected to the first cleaning liquid interface, and the other end of the first cleaning pipeline 8 is connected to the sampling pipeline 1. One end of the second cleaning pipeline 9 is connected to the second cleaning liquid interface, and the other end of the second cleaning pipeline 9 is connected to the automatic dilution device 3. One end of the purge pipeline 10 is connected to the purge gas interface, and the other end of the purge pipeline 10 is connected to the sampling pipeline 1. The first cleaning pipeline 8 is connected to the sampling pipeline 1 located upstream of the sampling pump 2, and the second cleaning pipeline 9 is connected to the sampling pipeline 1 located downstream of the sampling pump 2. That is, by setting up a self-cleaning system, the online sampling system after the sample measurement can be cleaned with a cleaning liquid to avoid contamination of the online sampling system during the sample measurement, thereby interfering with the accuracy of the next sample measurement.

[0036] Among them, a first control valve 11 is provided on the first cleaning pipeline 8, a second control valve 12 is provided on the second cleaning pipeline 9, and a third control valve 13 is provided on the purge pipeline 10. The first control valve 11, the second control valve 12 and the third control valve 13 are respectively electrically connected to the automatic control system 6. When the cleaning liquid is transported through the first cleaning pipeline 8, the transport power can be provided by the injection pump 2 provided on the injection pipeline 1. A cleaning liquid pump is also provided on the second cleaning pipeline 9, which is used to provide power when the cleaning liquid is transported through the first cleaning pipeline 8.

[0037] When in use, the online sampling system can be cleaned 2-3 times with a cleaning liquid, and then a certain pressure of purge gas is introduced through the purge pipe 10 to purge the cleaning liquid remaining in the online sampling system, so as to achieve thorough cleaning of the online sampling system and avoid cross contamination caused by measurement between samples. The automatic control system 6 can realize automatic switching of the cleaning liquid and the purge gas to control the self-cleaning system to perform automatic cleaning.

[0038] The self-cleaning system further includes a pure water pipeline 14, one end of which is connected to the pure water interface, and the other end of which is connected to the second cleaning pipeline 9. A fourth control valve 15 is provided on the pure water pipeline 14, and the fourth control valve 15 is electrically connected to the automatic control system 6. That is, the online sampling system can be further cleaned using pure water through the pure water pipeline 14.

[0039] Specifically, due to the difference in real-time uranium content, in order to ensure the representativeness of sampling, periodic sampling can be adopted. By setting an automatic dilution device 3 at the front end of the circulation pool 4, both the stability of the sampling and the quantitative dilution of the sample can be ensured. The circulation pool 4 is mainly used for the storage and detection of quantitative samples to be tested. The samples enter the circulation pool 4 in a top-in and bottom-out manner. Figure 2As shown, two projection windows are provided on the flow cell 4. The projection windows are made of carbon fiber, and are windows for the rays to enter the flow cell and windows for the characteristic rays of the sample to exit the flow cell. A collimation channel 16 is provided on one side of the projection window for the rays to enter the flow cell 4, and an X-ray tube 17 and a filter 18 in the graphite crystal pre-diffraction XRF measurement system 5 are respectively provided on the front side of the collimation channel 16. The collimation channel 16 can be provided to position and collimate the measurement component and the flow cell 4. The detector 19 and the graphite crystal 20 in the graphite crystal pre-diffraction XRF measurement system 5 are respectively provided on one side of the projection window for the characteristic rays to exit the flow cell 4.

[0040] like Figure 3 As shown, specifically, six flow cells 4 can be provided, corresponding to two injection lines of the aqueous phase and organic phase samples respectively and one blank sample pool of the aqueous phase and organic phase samples respectively. The six flow cells 4 are arranged in a ring shape on the turntable 29. When a certain sample needs to be measured, the turntable 29 automatically rotates so that the flow cell 4 to be measured is aligned with the X-ray emission device of the graphite crystal pre-diffraction XRF measurement system 5. The automatic control system 6 can realize the switching of sampling ports of different processes as needed, and realize real-time online and quantitative injection of waste liquid.

[0041] Therefore, the online measurement system for uranium content in waste liquid according to the embodiment of the present invention has a high degree of integration, can perform mobile measurement, can realize multi-point online measurement, greatly improves production efficiency, and effectively improves the automation level of analysis and detection.

[0042] Specifically, a pressure reducing valve 21, a quantitative valve 22 and a fifth control valve 23 are respectively provided on the sampling pipeline 1, and the pressure reducing valve 21, the quantitative valve 22 and the fifth control valve 23 are respectively electrically connected to the automatic control system 6, so that the sampling process of the online sampling system is automatically controlled by the automatic control system 6.

[0043] Specifically, the outlet of the automatic diluting device 3 is connected to the upper inlet of the circulation pool 4 through a diluent pipeline, and a sixth control valve 24 is provided on the diluent pipeline. The lower outlet of the circulation pool 4 is connected to a reflux pipeline 26, and a seventh control valve 25 is provided on the reflux pipeline 26. The sixth control valve 24 and the seventh control valve 25 are electrically connected to the automatic control system 6, respectively. After the detection is completed, the waste liquid sample in the circulation pool 4 can automatically return to the original sampling pipeline through the reflux pipeline 26.

[0044] Of course, the outlet at the lower end of the circulation pool 4 may also be connected to a waste liquid tank through a pipeline for centralized collection of waste liquid.

[0045] Furthermore, an exhaust duct 27 may be connected to the reflux duct 26, the exhaust duct 27 is connected to the exhaust port, and an eighth control valve 28 is provided on the exhaust duct 27, the eighth control valve 28 is electrically connected to the automatic control system 6. After the online sampling system is purged by the self-cleaning system, the purge gas may be discharged to the outside through the exhaust duct 27.

[0046] The working process of the online measurement system for uranium content in waste liquid according to the embodiment of the present invention is as follows:

[0047] The waste liquid from the waste liquid sampling port enters the sampling pipeline 1 through the sampling pump 2, and then enters the automatic diluting device 3, and then the valves on the sampling pipeline 1 and the sampling pump 2 are closed. After the waste liquid is diluted by the automatic diluting device 3, the sixth control valve 24 at the outlet of the automatic diluting device 3 is opened, and the sample in the automatic diluting device 3 enters the circulation pool 4. After the injection volume reaches the specified amount, the injection is stopped, and then the graphite crystal pre-diffraction XRF measurement system 5 is used to determine the uranium content of the waste liquid sample in the circulation pool 4. After the measurement is completed, the valves on the sampling pipeline 1 are started, and then the valves at the outlets of the automatic diluting device 3 and the circulation pool 4 are opened, so that the samples in the sampling pipeline 1, the automatic diluting device 3 and the circulation pool 4 are returned to the original sampling pipeline. Then the self-cleaning system is controlled to run, and the online sampling system after the sample measurement is cleaned 2 to 3 times by the cleaning liquid, and the cleaning waste liquid can be collected through the waste liquid tank. Then, a certain pressure of purge gas is blown into the online sampling system through the self-cleaning system to purge the residual cleaning liquid in the online sampling system, and the purged gas is discharged through the exhaust pipe 27.

[0048] Finally, it should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention, rather than to limit it. Although the present invention has been described in detail with reference to the aforementioned embodiments, those skilled in the art should understand that they can still modify the technical solutions described in the aforementioned embodiments, or replace some or all of the technical features therein with equivalents. However, these modifications or replacements do not cause the essence of the corresponding technical solutions to deviate from the scope of the technical solutions of the embodiments of the present invention.

Claims

1. An online measurement system for uranium content in waste liquid, characterized in that: The invention comprises an online sampling system, a detection system, an automatic control system and a DCS system. The online sampling system comprises a sampling pipeline, a sampling pump, an automatic diluting device and a circulation pool. One end of the sampling pipeline is connected to a sampling port of waste liquid, and the other end of the sampling pipeline is connected to the automatic diluting device, which is connected to the circulation pool. The detection system comprises a graphite crystal pre-diffraction XRF measurement system, which corresponds to the circulation pool, is electrically connected to the automatic control system, and the automatic control system is electrically connected to the DCS system.

2. The system for online measurement of uranium content in waste liquid according to claim 1, characterized in that: It also includes a self-cleaning system, which includes a first cleaning pipe, a second cleaning pipe and a purge pipe, one end of the first cleaning pipe is connected to a first cleaning liquid interface, and the other end of the first cleaning pipe is connected to the injection pipe; one end of the second cleaning pipe is connected to a second cleaning liquid interface, and the other end of the second cleaning pipe is connected to the automatic dilution device; one end of the purge pipe is connected to a purge gas interface, and the other end of the purge pipe is connected to the injection pipe.

3. The system for online measurement of uranium content in waste liquid according to claim 2, characterized in that: A first control valve is provided on the first cleaning pipeline, a second control valve is provided on the second cleaning pipeline, and a third control valve is provided on the purge pipeline. The first control valve, the second control valve and the third control valve are electrically connected to the automatic control system respectively.

4. The system for online measurement of uranium content in waste liquid according to claim 2, characterized in that: The self-cleaning system further comprises a pure water pipeline, one end of which is connected to a pure water interface, and the other end of which is connected to the second cleaning pipeline.

5. The system for online measurement of uranium content in waste liquid according to claim 4, characterized in that: A fourth control valve is provided on the pure water pipeline, and the fourth control valve is electrically connected to the automatic control system.

6. The system for online measurement of uranium content in waste liquid according to claim 2, characterized in that: A cleaning liquid pump is also provided on the second cleaning pipeline.

7. The system for online measurement of uranium content in waste liquid according to claim 1, characterized in that: A pressure reducing valve, a quantitative valve and a fifth control valve are respectively arranged on the sampling pipeline, and the pressure reducing valve, the quantitative valve and the fifth control valve are respectively electrically connected to the automatic control system.

8. The system for online measurement of uranium content in waste liquid according to claim 1, characterized in that: The outlet of the automatic dilution device is connected to the upper inlet of the circulation pool through a diluent pipeline, and a sixth control valve is arranged on the diluent pipeline, and the sixth control valve is electrically connected to the automatic control system.

9. The system for online measurement of uranium content in waste liquid according to claim 1, characterized in that: The lower outlet of the circulation pool is connected to a reflux pipeline, a seventh control valve is arranged on the reflux pipeline, and the seventh control valve is electrically connected to the automatic control system.

10. The system for online measurement of uranium content in waste liquid according to claim 9, characterized in that: It also includes an exhaust duct, one end of which is connected to the return duct, and the other end of which is connected to the exhaust port; an eighth control valve is arranged on the exhaust duct, and the eighth control valve is electrically connected to the automatic control system.

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