Radioactive waste liquid activity measuring device and control method

Abstract

The invention relates to a radioactive waste liquid activity measuring device and a control method, in particular to the field of radiation monitoring, and the radioactive waste liquid activity measuring device sequentially comprises a display area, a sample measuring area and a functional area from top to bottom; the sample measuring area comprises a sample chamber and a detector assembly; the sample chamber is provided with a sample waste liquid level detection device, an overflow detection device and cleaning equipment; the sample chamber comprises a protection cavity and a Marinin cup-shaped sample box; the detector assembly is positioned above the Marinin cup-shaped sample box; a power supply module, a sample feeding / discharging pump and a low-level liquid level detection device are arranged in the functional area; the medical radioactive waste liquid decay pool is connected with the sample chamber through the sample injection / discharge pump; and the low liquid level detection device is arranged on a pipeline for connecting the sample injection / discharge pump and the Marinin cup-shaped sample box. The measuring device provided by the invention can accurately measure the activity of radionuclides in the waste liquid, and the device can realize that the measuring result can be traced to the national social public measurement standard through accurate measurement, so that the reliability is guaranteed.

Description

Technical Field

[0001] The invention relates to the field of radiation monitoring, and in particular to a device for measuring the activity of radioactive waste liquid and a control method. Background Art

[0002] Medical radioactive liquid waste refers to liquid containing radionuclides produced in open radiation workplaces such as nuclear medicine, medical and biological laboratories, mainly from three sources:

[0003] (1) Excrement of patients waiting for treatment or in hospital after taking radioactive drugs during nuclear medicine diagnosis and treatment;

[0004] (2) Decontamination washing liquid produced by cleaning;

[0005] (3) Radioactive wastewater discharged from the preparation of medical marker compounds and the disposal of excess doses of radioactive isotopes.

[0006] There are currently three main methods for measuring the activity of medical radioactive waste:

[0007] (1) Immersed real-time online monitoring, that is, the detector is immersed in the decay pool for measurement. A Geiger counter or scintillator detector is usually used. In order to prevent the medical radioactive waste from corroding the detector, the detector surface is often covered with corrosion-resistant protective materials.

[0008] (2) Post-sampling laboratory analysis, i.e. sampling at the site of the medical radioactive waste decay pool and then sending it to a qualified laboratory for measurement and analysis;

[0009] (3) Physical decay method, i.e. after the medical radioactive waste liquid is stored in a decay pool, its activity decays over time in a negative exponential law according to the half-life of the main nuclides therein. The temporary storage time of radioactive waste liquid containing nuclides with a half-life greater than 24 hours exceeds 10 times the longest half-life (the temporary storage time of iodine-131 nuclides exceeds 180 days). After the monitoring results are approved by the review and supervision department, they are discharged into the environment in accordance with the method specified in 8.6.2 of GB18871.

[0010] However, in immersion real-time online monitoring, it is impossible to use standard materials with the same geometry, matrix and volume as the decay cell for efficiency calibration. Therefore, this method can only qualitatively indicate the strength of the radioactive activity in the waste liquid, but cannot accurately quantify the activity of the radioactive nuclides. Furthermore, if the detector fails, it may not be able to be replaced in a short time, and there is a risk of monitoring gaps.

[0011] Alternatively, the on-site sampling method is used and then sent to the laboratory for analysis. However, a large amount of decay will occur during the transportation of the samples to the laboratory for analysis and during the long sample preparation process, resulting in the final measurement result being far lower than the actual activity, which is not suitable for 18 F and99m Activity measurement of short half-life nuclides such as Tc, 131 Although the half-life of I is relatively long, it is only 8 days. On the other hand, the main radionuclides in current medical radioactive waste liquid are 131 I, with volatile characteristics, according to the measurement method specified in GB18466-2005, using EJ / T900-1994 "Evaporation method for determination of total β radioactivity in water", will result in 131 I is completely volatilized during the laboratory pretreatment of the total α and total β samples, so the results are far lower than the actual true values.

[0012] In summary, the current detection of activity of medical waste liquid still has the defects of poor activity detection accuracy and inability to effectively measure. Summary of the invention

[0013] In view of the problems existing in the prior art, the purpose of the present invention is to provide a device and a control method for measuring the activity of radioactive waste liquid, so as to solve the defects of poor activity detection accuracy and inability to effectively measure the activity of medical waste liquid.

[0014] To achieve this object, the present invention adopts the following technical solutions:

[0015] In a first aspect, the present invention provides a device for measuring the activity of radioactive waste liquid, the device comprising, from top to bottom:

[0016] Display area, sample measurement area and function area;

[0017] The sample testing area includes a sample chamber and a detector assembly;

[0018] The sample chamber is equipped with a sample waste liquid level detection device, an overflow detection device and a cleaning device;

[0019] The sample chamber includes a protective cavity and a Marlin cup-shaped sample box;

[0020] The detector assembly is located above the Marlin cup-shaped sample box;

[0021] The overflow detection device is used to detect whether the material in the Marlin cup sample box overflows into the outside of the sample chamber;

[0022] The functional area is provided with a power supply module, a sample injection / discharge pump and a low liquid level detection device;

[0023] The medical radioactive waste liquid decay pool is connected to the sample chamber via the sample injection / discharge pump;

[0024] The low liquid level detection device is arranged on a pipeline connecting the sample injection / discharge pump and the Marlin cup-shaped sample box.

[0025] The measuring device provided by the present invention can accurately measure the activity of radioactive nuclides in waste liquid, and enables the device to achieve traceability of measurement results to national social public measurement standards through accurate measurement, so that reliability is guaranteed. At the same time, in order to reduce transportation risks and improve the accuracy of the activity of short-lived nuclides in waste liquid, a dynamic sampling and cleaning function is added, and multiple continuous sampling and measurement can be completed on site, which greatly improves work efficiency and result accuracy.

[0026] As a preferred technical solution of the present invention, the display area is configured with a display module and / or a wireless module;

[0027] Preferably, the display module includes an embedded display module or an external display module;

[0028] Preferably, the display module is connected to the control center via a cable;

[0029] Preferably, the wireless module is connected to the wireless display module / or the wireless control module by wireless communication;

[0030] Preferably, the control center is connected to the sample waste liquid level detection device, the overflow detection device, the low level detection device, the sample injection / discharge pump and the cleaning equipment respectively.

[0031] As a preferred technical solution of the present invention, the detector assembly includes a scintillator detector and a multi-channel analyzer;

[0032] Preferably, the sample waste liquid level detection device is a movable liquid level detection device.

[0033] As a preferred technical solution of the present invention, the cleaning device comprises a washing liquid feeding end and a washing liquid pump connected in sequence;

[0034] Preferably, the washing liquid pump is connected to the sample chamber via a one-way valve.

[0035] As a preferred technical solution of the present invention, the power supply module includes a DC power supply device and / or a storage power supply device;

[0036] Preferably, the power storage and power supply device is equipped with a power display module and / or a charging module.

[0037] As a preferred technical solution of the present invention, the measuring device is further configured with a working status indication module and / or an emergency stop module.

[0038] In a second aspect, the present invention provides a control method for a device for measuring the activity of radioactive waste liquid, the control method comprising:

[0039] S1, power on self-test, set parameters and perform spectrum stabilization, then collect background spectrum;

[0040] S2, perform background spectrum verification and energy calibration;

[0041] S3. Draw samples to the preset liquid level, complete the test and analyze the data to obtain the activity.

[0042] As a preferred technical solution of the present invention, the power-on self-check includes: powering on to detect whether there is residual liquid in the sample chamber, if so, cleaning and draining the liquid, otherwise collecting background spectrum.

[0043] As a preferred technical solution of the present invention, the background spectrum verification includes identifying characteristic energy peaks and / or counting anomaly verification.

[0044] Preferably, the identification characteristic energy peak includes: if the obtained background spectrum fails to identify 40 K or 138 The characteristic energy peak of La is detected, and the background measurement time is extended until the 40 K or 138 Energy calibration is performed after the characteristic energy peak of La.

[0045] Preferably, the counting abnormality verification includes cleaning at least twice and collecting the background spectrum until the counting is normal if there is counting abnormality in the obtained background spectrum.

[0046] Preferably, the counting anomaly includes the full spectrum counting rate being greater than 1.3 times the initial background counting rate and / or the presence of 40 K or 138 Other energy peaks besides the characteristic energy peak of La;

[0047] Preferably, the energy scale includes markings 40 K characteristic energy peak is 1460keV and / or marker detector isotope composition 138 The characteristic energy peak of La is 1435.8 keV.

[0048] As a preferred technical solution of the present invention, after the detection is completed, the sample chamber is drained and cleaned at least twice;

[0049] Preferably, if after the cleaning is completed, a characteristic energy peak of the medical nuclide to be measured appears in the detector measurement spectrum or the spectrum count rate is greater than the background spectrum count rate, cleaning is performed again until the characteristic energy peak of the medical nuclide to be measured disappears or the increase in the full spectrum count rate is ≤30% of the background spectrum count rate, the cleaning is completed;

[0050] Preferably, if after the cleaning is completed, 131 The activity of I is recorded 131 The activity of I is removed when measuring again 131 The decay value of I.

[0051] Compared with the prior art solutions, the present invention has the following beneficial effects:

[0052] (1) By configuring a high-sensitivity liquid level sensor, the sampling of medical radioactive waste liquid on site can be automated. After the measurement, the sample can be arranged without disassembly, which greatly shortens the time personnel are exposed to radiation and reduces the risk of radiation dose. At the same time, the efficiency of analysis and measurement is improved. At the same time, the traceability of the radioactive activity value of the nuclides in the waste liquid is achieved, and the result deviation is less than 1.5%.

[0053] (2) A cleaning nozzle is designed on the top of the sample box. After the measurement is completed, the sample box can be cleaned without disassembly. The cleaning efficiency is over 85%. The cleaning liquid can be directly discharged into the decay pool on site without the burden of subsequent treatment of radioactive cleaning waste liquid. At the same time, it can reduce the background interference of different measurement results during continuous operation and extend the service life of the sample box.

[0054] (3) The "probe on top and sample on bottom" structure reduces the impact of environmental radiation while reducing the probability of collision damage to the probe surface and reducing the shielding material. The environmental radiation shielding rate reaches more than 84%. BRIEF DESCRIPTION OF THE DRAWINGS

[0055] Figure 1 is a schematic diagram of a device for measuring the activity of radioactive waste liquid provided by an embodiment of the present invention;

[0056] Figure 2 It is a flow chart of a control method of a device for measuring activity of radioactive waste liquid provided by an embodiment of the present invention;

[0057] Figure 3 It is a schematic diagram of the measuring device actually used in Example 1 of the present invention.

[0058] In the figure: 1-display area, 2-sample measurement area, 2.1-washing liquid pump, 2.2-control center, 2.3-sample chamber, 2.4-sample waste liquid level detection device, 3-functional area, 3.1-power display module, 3.2-power supply module, 3.3-low level detection device, 3.4-intake / discharge pump, 4-working status indication module, 5-emergency stop module.

[0059] The present invention is further described in detail below. However, the following examples are only simplified examples of the present invention and do not represent or limit the scope of protection of the present invention. The scope of protection of the present invention shall be subject to the claims. DETAILED DESCRIPTION

[0060] To better illustrate the present invention and facilitate understanding of the technical solution of the present invention, typical but non-limiting embodiments of the present invention are as follows:

[0061] This embodiment provides a device for measuring the activity of radioactive waste liquid, such as Figure 1 As shown, the measuring device comprises:

[0062] Display area 1, sample area 2 and function area 3;

[0063] The sample measurement area 2 includes a sample chamber 2.3 and a detector assembly;

[0064] The sample chamber 2.3 is equipped with a sample waste liquid level detection device 2.4, an overflow detection device and a cleaning device;

[0065] The sample chamber 2.3 includes a protective cavity and a Marlin cup-shaped sample box;

[0066] The detector assembly is located above the Marlin cup-shaped sample box;

[0067] The overflow detection device is used to detect whether the material in the Marlin cup-shaped sample box overflows into the outside of the sample chamber 2.3;

[0068] The functional area 3 is provided with a power supply module 3.2, a sample injection / discharge pump 3.4 and a low liquid level detection device 3.3;

[0069] The medical radioactive waste liquid decay pool is connected to the sample chamber 2.3 via the sample injection / discharge pump 3.4;

[0070] The low liquid level detection device 3.3 is arranged on the pipeline connecting the sample injection / discharge pump 3.4 and the Marlin cup-shaped sample box.

[0071] In the present invention, the sample waste liquid level detection device 2.4 is used to monitor whether the waste liquid taken has reached the set amount. At the same time, it can be movable to further meet the needs of sample liquid volume when different radioactive waste liquids are detected. The low level detection device 3.3 is used to monitor whether the waste liquid taken has been drained. The overflow detection device is used to prevent the sample waste liquid level detection device 2.4 from failing. When the sample waste liquid level detection device 2.4 fails, the liquid level reaches this point and an instruction is issued, at which time the sample injection / discharge pump 3.4 stops taking waste liquid.

[0072] Specifically, the display area 1 is configured with a display module and / or a wireless module.

[0073] Specifically, the display module includes an embedded display module or an external display module. It is used to display the test results and control the operation of the device. Furthermore, the wireless module can be used to control the test process and monitor the detection device by wireless remote operation, and can also be connected to an intelligent control system to realize intelligent control of the device, such as joint control with the discharge end to realize the linkage between discharge and detection.

[0074] Specifically, the display module is connected to the control center 2.2 via a cable.

[0075] Specifically, the wireless module is connected to the wireless display module / or the wireless control module by wireless communication;

[0076] Specifically, the control center 2.2 is connected to the sample waste liquid level detection device 2.4, the overflow detection device, the low level detection device 3.3, the sample injection / discharge pump 3.4 and the cleaning device. The control center 2.2 realizes the joint logic control of each device in the device, which is conducive to the intelligent and stable operation of the device.

[0077] Specifically, the detector assembly includes a scintillator detector and a multi-channel analyzer.

[0078] Specifically, the sample waste liquid level detection device 2.4 is a movable liquid level detection device.

[0079] Specifically, the cleaning device comprises a cleaning liquid inlet and a cleaning liquid pump 2.1 which are connected in sequence.

[0080] Preferably, the washing liquid pump 2.1 is connected to the sample chamber 2.3 via a one-way valve.

[0081] Specifically, the power supply module 3.2 includes a DC power supply device and / or a storage power supply device.

[0082] Specifically, the power storage and power supply device is equipped with a power display module 3.1 and / or a charging module.

[0083] Specifically, the measuring device is also equipped with a working state indicating module 4 and / or an emergency stop module 5. By configuring the working state indicating module 4, it is possible to intuitively confirm whether the measuring device is operating reasonably. By using the emergency stop module 5, when a detection error or an operation error occurs, the device can be emergency stopped and the discharge can be stopped simultaneously.

[0084] Furthermore, the present invention provides a control method for the aforementioned dynamic measurement device, the process is as follows Figure 2 As shown, the control method includes:

[0085] S1, power on self-test, set parameters and perform spectrum stabilization, then collect background spectrum;

[0086] S2, perform background spectrum verification and energy calibration;

[0087] S3. Draw samples to the preset liquid level, complete the test and analyze the data to obtain the activity.

[0088] The power-on self-check includes: powering on to detect whether there is residual liquid in the sample chamber 2.3, if so, cleaning and draining the liquid, otherwise collecting the background spectrum.

[0089] In the present invention, parameter setting includes: hardware initialization self-check, setting the last high voltage and magnification, and detecting whether the sample volume, probe selection, measurement time and measurement location have been modified.

[0090] In the present invention, spectrum stabilization is used to ensure that under different environmental conditions, such as temperature changes, the voltage change of the detector output is controlled, thereby ensuring the stability of the energy spectrum, and can be carried out according to the conventional requirements in the field.

[0091] In the present invention, spectrum data will be obtained after the detection is completed. The activity of the detected sample can be obtained by analyzing the data. At the same time, relevant data such as energy spectrum data, GPS data, activity, nuclides, etc. can be saved to facilitate data verification.

[0092] Wherein, the background spectrum verification includes identifying characteristic energy peaks and / or counting anomaly verification.

[0093] Wherein, the identification characteristic energy peak includes: if the obtained background spectrum fails to identify 40 K or 138 The characteristic energy peak of La is detected, and the background measurement time is extended until the 40 K or 138 Energy calibration is performed after the characteristic energy peak of La.

[0094] The counting abnormality verification includes cleaning at least twice and collecting the background spectrum until the counting is normal if there is counting abnormality in the obtained background spectrum.

[0095] The counting anomaly includes the full spectrum counting rate being greater than 1.3 times the initial background counting rate and / or the presence of 40 K or 138 Other energy peaks besides the characteristic energy peak of La.

[0096] Wherein, the energy scale includes a mark 40 The characteristic energy peak of K is 1460keV and / or the isotopic composition of the marker detector 138 The characteristic energy peak of La is 1435.8keV.

[0097] After the detection is completed, the sample chamber 2.3 is drained and cleaned at least twice.

[0098] Among them, if a characteristic energy peak of the medical nuclide to be measured appears in the detector measurement spectrum after the cleaning is completed or the spectrum counting rate is greater than the background spectrum counting rate, cleaning is performed again until the characteristic energy peak of the medical nuclide to be measured disappears or the increase in the full spectrum counting rate is ≤30% of the background spectrum counting rate (the background spectrum counting rate is the counting rate obtained by collecting the background spectrum after stabilizing the spectrum), and the cleaning is completed.

[0099] Wherein, if the sample chamber 2.3 is detected after the cleaning is completed 131 The activity of I is recorded 131 The activity of I is removed when measuring again 131 The decay value of I.

[0100] Further, in order to illustrate the measurement effect that can be achieved by the dynamic measurement device provided by the present invention, the following actual example is used for exemplary description, as follows:

[0101] Example 1

[0102] This embodiment provides a process of measuring using a dynamic measuring device, and the measuring device used is as follows:

[0103] Display area 1, sample area 2 and function area 3;

[0104] The sample measurement area 2 includes a sample chamber 2.3 and a detector assembly;

[0105] The sample chamber 2.3 is equipped with a sample waste liquid level detection device 2.4, an overflow detection device and a cleaning device;

[0106] The sample chamber 2.3 includes a protective cavity and a Marlin cup-shaped sample box;

[0107] The detector assembly is located above the Marlin cup-shaped sample box;

[0108] The overflow detection device is used to detect whether the material in the Marlin cup-shaped sample box overflows into the outside of the sample chamber 2.3;

[0109] The functional area 3 is provided with a power supply module 3.2, a sample injection / discharge pump 3.4 and a low liquid level detection device 3.3;

[0110] The medical radioactive waste liquid decay pool is connected to the sample chamber 2.3 via the sample injection / discharge pump 3.4;

[0111] The low liquid level detection device 3.3 is arranged on the pipeline connecting the sample injection / discharge pump 3.4 and the Marlin cup-shaped sample box.

[0112] Among them, the sample waste liquid level detection device 2.4 is used to monitor whether the waste liquid taken reaches the set amount. At the same time, it can be movable to further meet the needs of sample liquid volume when different radioactive waste liquids are detected. The low level detection device 3.3 is used to monitor whether the waste liquid taken is drained clean. The overflow detection device is used to prevent the sample waste liquid level detection device 2.4 from failing. When the sample waste liquid level detection device 2.4 fails, when the liquid level reaches the overflow level threshold, the sample injection / discharge pump 3.4 stops taking waste liquid.

[0113] Wherein, the display area 1 is configured with a display module.

[0114] The display module is an embedded display module, which is used to display the detection results and control the operation of the device. The display module is connected to the control center 2.2 via a cable.

[0115] The control center 2.2 is connected to the sample waste liquid level detection device 2.4, the overflow detection device, the low level detection device 3.3, the sample injection / discharge pump 3.4 and the cleaning device respectively. The control center 2.2 realizes the joint logic control of each device in the device, which is conducive to the intelligent and stable operation of the device.

[0116] The detector assembly includes a scintillator detector and a multi-channel analyzer.

[0117] The cleaning device comprises a washing liquid inlet and a washing liquid pump 2.1 which are connected in sequence; the washing liquid pump 2.1 is connected to the sample chamber 2.3 via a one-way valve.

[0118] The power supply module 3.2 includes a DC power supply device and a storage power supply device, and the storage power supply device is equipped with a power display module 3.1 and a charging module.

[0119] The measuring device is also equipped with a working state indicating module 4 and an emergency stop module 5. The working state indicating module 4 can be used to intuitively confirm whether the measuring device is operating properly. The emergency stop module 5 can realize the emergency stop of the device and simultaneously stop the discharge of liquid when a detection error or an operation error occurs.

[0120] The specific process is as follows:

[0121] 1. Configure LaBr 3 (Ce) detector (a scintillator detector) radioactive waste activity measurement device (such as Figure 3 The instrument was moved to the decay pool of a hospital, and then started to preheat and began to stabilize the spectrum. After completion, the background spectrum was measured and saved.

[0122] 2. Place one end of the hose into the waste liquid decay pool, and connect the other end to the sampling interface of the device. Then click the peristaltic pump start command to start extracting waste liquid into the sample box. When the liquid level reaches 1L, the peristaltic pump automatically stops sampling.

[0123] 3. Set the multi-channel parameters of the detector, enter the measurement time, high voltage and other parameters, click the start measurement command, and the detector part of the device will start spectral measurement.

[0124] 4. After the measurement is completed, save the measured spectrum, and then analyze the peak positions in the spectrum. The results are shown in Table 1 below.

[0125] Table 1

[0126]

[0127]

[0128] 5. To discharge the waste liquid, the peristaltic pump starts to rotate in the reverse direction to extract the waste liquid in the sample box into the decay pool. When the liquid level drops to the low level, the sensor corresponding to the low level detection device automatically sends a command and the peristaltic pump stops running.

[0129] 6. Connect one end of the cleaning hose to the clean water bucket and the other end to the flushing inlet on the top of the sample box, then click the cleaning command. The cleaning pump starts, and clean water enters the sample box through the three nozzles installed on the top of the sample box to clean the sample box. At the same time, the peristaltic pump automatically starts the drainage function. Each cleaning lasts 15 seconds, and the cleaning stops after two consecutive cleanings.

[0130] 7. Click Spectrum Measurement again and check the cleaning status through the spectrum. If the background count rate is higher than the background count rate in step 1, click the Cleaning command again to perform cleaning.

[0131] 8. Repeat steps 6 and 7 until the increase in the full spectrum count rate is no more than 30% of the background spectrum count rate obtained in step 1, and the measurement is completed.

[0132] The preferred embodiments of the present invention are described in detail above. However, the present invention is not limited to the specific details in the above embodiments. Within the technical concept of the present invention, a variety of simple modifications can be made to the technical solution of the present invention, and these simple modifications all belong to the protection scope of the present invention.

[0133] It should also be noted that the various specific technical features described in the above specific embodiments can be combined in any suitable manner without contradiction. In order to avoid unnecessary repetition, the present invention will not further describe various possible combinations.

[0134] In addition, various embodiments of the present invention may be arbitrarily combined, and as long as they do not violate the concept of the present invention, they should also be regarded as the contents disclosed by the present invention.

Claims

1. A device for measuring the activity of radioactive waste liquid, characterized in that: The measuring device comprises, from top to bottom: Display area, sample measurement area and function area; The sample testing area includes a sample chamber and a detector assembly; The sample chamber is equipped with a sample waste liquid level detection device, an overflow detection device and a cleaning device; The sample chamber includes a protective cavity and a Marlin cup-shaped sample box; The detector assembly is located above the Marlin cup-shaped sample box; The overflow detection device is used to detect whether the material in the Marlin cup sample box overflows into the outside of the sample chamber; The functional area is provided with a power supply module, a sample injection / discharge pump and a low liquid level detection device; The medical radioactive waste liquid decay pool is connected to the sample chamber via the sample injection / discharge pump; The low liquid level detection device is arranged on a pipeline connecting the sample injection / discharge pump and the Marlin cup-shaped sample box.

2. The device for measuring the activity of radioactive waste liquid according to claim 1, characterized in that: The display area is configured with a display module and / or a wireless module; Preferably, the display module includes an embedded display module or an external display module; Preferably, the display module is connected to the control center via a cable; Preferably, the wireless module is connected to the wireless display module / or the wireless control module by wireless communication; Preferably, the control center is connected to the sample waste liquid level detection device, the overflow detection device, the low level detection device, the sample injection / discharge pump and the cleaning equipment respectively.

3. The device for measuring the activity of radioactive waste liquid according to claim 1 or 2, characterized in that: The detector assembly includes a scintillator detector and a multi-channel analyzer; Preferably, the sample waste liquid level detection device is a movable liquid level detection device.

4. The device for measuring the activity of radioactive waste liquid according to any one of claims 1 to 3, characterized in that: The cleaning device comprises a washing liquid inlet and a washing liquid pump connected in sequence; Preferably, the washing liquid pump is connected to the sample chamber via a one-way valve.

5. The device for measuring the activity of radioactive waste liquid according to any one of claims 1 to 4, characterized in that: The power supply module includes a DC power supply device and / or a storage power supply device; Preferably, the power storage and power supply device is equipped with a power display module and / or a charging module.

6. The device for measuring the activity of radioactive waste liquid according to any one of claims 1 to 5, characterized in that: The measuring device is also equipped with a working status indication module and / or an emergency stop module.

7. A control method for a device for measuring the activity of radioactive waste liquid, characterized in that: The control method comprises: S1, power on self-test, set parameters and perform spectrum stabilization, then collect background spectrum; S2, perform background spectrum verification and energy calibration; S3. Draw samples to the preset liquid level, complete the test and analyze the data to obtain the activity.

8. The control method according to claim 7, characterized in that: The power-on self-check includes: powering on to detect whether there is residual liquid in the sample chamber, if so, cleaning and draining the liquid, otherwise collecting the background spectrum.

9. The control method according to claim 7 or 8, characterized in that: The background spectrum verification includes identifying characteristic energy peaks and / or counting anomaly verification; Preferably, the identification characteristic energy peak includes: if the obtained background spectrum fails to identify 40 K or 138 The characteristic energy peak of La is detected, and the background measurement time is extended until the 40 K or 138 Energy calibration is performed after the characteristic energy peak of La; Preferably, the counting abnormality verification includes, if there is a counting abnormality in the obtained background spectrum, cleaning at least twice and collecting the background spectrum until the counting is normal; Preferably, the counting anomaly includes the full spectrum counting rate being greater than 1.3 times the initial background counting rate and / or the presence of 40 K or 138 Other energy peaks besides the characteristic energy peak of La; Preferably, the energy scale includes markings 40 K characteristic energy peak is 1460keV and / or marker detector isotope composition 138 The characteristic energy peak of La is 1435.8 keV.

10. The control method according to any one of claims 7 to 9, characterized in that: After the detection is completed, the sample chamber is drained and cleaned at least twice; Preferably, if after the cleaning is completed, a characteristic energy peak of the medical nuclide to be measured appears in the detector measurement spectrum or the spectrum count rate is greater than the background spectrum count rate, cleaning is performed again until the characteristic energy peak of the medical nuclide to be measured disappears or the increase in the full spectrum count rate is ≤30% of the background spectrum count rate, the cleaning is completed; Preferably, if after the cleaning is completed, 131 The activity of I is recorded 131 The activity of I is removed when measuring again 131 The decay value of I.

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