Radioactive liquid waste sampling and measuring device and system

Abstract

This invention discloses a radioactive waste liquid sampling and measurement device and system, belonging to the field of waste liquid sampling and measurement technology. The invention includes a sealed chassis with a rotating top plate on top. A top frame and a gas storage bladder frame are located at the center of the top of the rotating top plate. A sampling column and a cap-removing cylinder are sleeved on the top frame. A push rod is slidably sleeved inside the cap-removing cylinder, and a sleeve plate extending into the sealed chassis is located at the bottom of the push rod. The device, through the construction of a sealed environment, the double-fixed opening and closing of the sealed cover, and the quantitative sealing design of the sampling cylinder, prevents waste liquid leakage, splashing, and radioactive gas diffusion during sampling. The system relies on multi-module collaboration to achieve multi-dimensional data acquisition. By quantifying corrosion, leakage, and sampling exposure risks, it intelligently generates risk warnings, and the data is traceable, significantly improving sampling safety, reliability, and the standardization of nuclear facility waste liquid management.

Description

Technical Field

[0001] This invention relates to the field of waste liquid sampling and measurement technology, specifically to a radioactive waste liquid sampling and measurement device and sampling and measurement system. Background Technology

[0002] In nuclear industry production, nuclear facility operation, and nuclear research activities, radioactive waste containing various radionuclides is inevitably generated. This type of waste has significant characteristics such as high radioactivity, high toxicity, and long-term harmful effects. If not handled properly or discharged in excess, it can cause serious and lasting harm to the ecological environment and human health. Radioactive waste containers are usually used for its storage and sealing. Accurate monitoring of key parameters such as the radioactivity and nuclide composition of radioactive waste is an important prerequisite for ensuring the safe operation of nuclear facilities, implementing environmental emission requirements, and carrying out subsequent treatment and disposal of waste. The core link in achieving this monitoring goal is to conduct scientific and reasonable sampling and accurate measurement of radioactive waste.

[0003] Traditional sampling equipment suffers from two major problems in radioactive waste sampling: structural design flaws and insufficient system support. Structurally, it lacks a reliable, sealed sampling environment. During sampling, the opening and closing of the storage tank's sealing cover is directly exposed to the outside, and the seals are easily corroded and aged by strong acids and alkalis in the waste liquid, leading to loosening of the interfaces. Simultaneously, traditional sampling mechanisms cannot accurately control sampling depth and volume. Pressure fluctuations within the equipment caused by high-viscosity waste liquid or decaying gases can easily lead to waste liquid dripping and splashing during sampling. There is also a lack of effective means to collect overflowing radioactive gases, potentially causing serious radioactive exposure hazards. System-wise, traditional sampling relies solely on manual operation and post-sampling inspection, lacking multi-dimensional data collection and integrated analysis of device operation, container status, and waste liquid characteristics. It cannot quantify potential risks such as container corrosion and leakage, nor can it predict trends in waste liquid radioactivity levels, leading to misjudgments of sampling risks, failure to identify hidden dangers in advance, and a lack of traceability in sampling data, making it difficult to support subsequent waste liquid treatment and nuclear facility safety management decisions.

[0004] To address the aforementioned technical shortcomings, a solution is proposed. Summary of the Invention

[0005] The purpose of this invention is to provide a radioactive waste liquid sampling and measuring device and a sampling and measuring system to solve the problems mentioned above.

[0006] To achieve the above objectives, the present invention provides the following technical solution: a radioactive waste liquid sampling and measuring device, comprising a sealed base, a rotating top plate being provided on the top of the sealed base, a top frame and a gas storage bag frame being provided at the center of the top of the rotating top plate, a sampling column and a cap-removing cylinder being sleeved on the top frame, a push rod being slidably sleeved inside the cap-removing cylinder, and a sleeve plate extending into the interior of the sealed base being provided at the bottom of the push rod;

[0007] The sampling column has a back plate on its back side, and a slider is slidably arranged between the sampling column and the back plate. A lead screw is embedded inside the front column body of the sampling column, and a sampling cylinder is provided at the bottom of the slider. A locking cone is slidably sleeved at the bottom of the sampling cylinder.

[0008] Furthermore, a sealing gasket is embedded in the bottom cross section of the sealing chassis, an air intake ring is provided on the inner wall of the bottom of the sealing chassis, and a slide rail is provided on the top of the sealing chassis to cooperate with and connect with the rotating top plate.

[0009] Furthermore, a sliding sleeve is provided at the bottom of the rotating top plate, several sets of brackets are provided on the outer wall of the top frame, an adapter port corresponding to each set of brackets is provided through the top of the rotating top plate, an air exchange port is provided at the bottom of the air storage bag frame through the rotating top plate, a control pull ring is provided on the outer wall of the top of the air storage bag frame, and a circulating air pump is provided inside the air storage bag frame, and the circulating air pump is connected to the air exchange port and the air inlet ring by a pipeline.

[0010] Furthermore, the bottom surface of the cover-removing cylinder is provided with a matching bottom pad that fits into the rotating top plate, the top of the plate is provided with a fixing locking rod that fits into the bottom of the push rod, a sliding rod is slidably fitted inside the fixing locking rod, a suction cup is provided at the bottom of the sliding rod, multiple sets of rotating shafts are arranged in a ring array on the inner wall of the plate, a rotating clamp is hinged on the rotating shaft, and a traction wire connecting the rotating shaft and the rotating clamp is provided at the top of the sliding rod.

[0011] Furthermore, a micro motor is embedded in one corner of the top front of the sampling column and is connected to the lead screw for transmission. A roller is sleeved on the surface of the lead screw. A limiting locking plate is installed through the middle of the slider and is engaged with the roller. Long grooves are symmetrically arranged on both sides of the sampling column, and several sets of holes are evenly spaced inside the long grooves. A locking block is installed inside the long groove and engages with the holes. Side blocks are symmetrically arranged on the outer walls of both sides of the slider. A sliding beam is movably sleeved on the top of the slider. A pull rod connected to the locking cone is provided at the bottom of the sliding beam. An annular groove is recessed on the inner wall of the bottom of the sampling cylinder. An adapter base pad is provided at the bottom of the sampling column and is connected to the rotating top plate.

[0012] A radioactive waste liquid sampling and measurement system includes a measurement and monitoring center, a multi-source measurement data acquisition module, a container safety analysis module, and a waste liquid sampling risk module. Each module communicates bidirectionally via a data transmission link. The multi-source measurement data acquisition module collects raw data from the radioactive waste liquid and storage tanks and transmits it to the container safety analysis module and the measurement and monitoring center. The container safety analysis module performs joint analysis on container-related sub-data in the raw data to generate a container safety judgment signal, which is simultaneously transmitted to the waste liquid sampling risk module and the measurement and monitoring center. The waste liquid sampling risk module combines the waste liquid-related sub-data in the raw data with the container safety judgment signal, performs data comparison and conversion analysis to generate a waste liquid sampling safety signal, which is transmitted to the measurement and monitoring center. The measurement and monitoring center summarizes the received signals to generate a complete sampling report.

[0013] Furthermore, the working process of the multi-source data acquisition module is as follows:

[0014] Based on the sealed environment created by installing a sampling and measurement device on the storage tank, and combined with the sensors deployed within the sampling and measurement device, the data acquisition range is defined to obtain sampling device operation data, storage tank status data, and radioactive waste liquid characteristic data. Real-time acquisition of sampling device operation data includes sealed environment pressure, sampling depth of the sampling cylinder, locking cone sealing pressure, and gas activity collected by the gas storage bladder. Real-time acquisition of storage tank status data includes internal tank pressure, tank wall temperature, tank wall thickness, external surface dose rate, and leachate radioactivity activity from the leak monitoring sensor. Real-time acquisition of radioactive waste liquid characteristic data includes total alpha activity concentration, total beta activity concentration, characteristic nuclide activity concentration, waste liquid pH value, suspended solids content, and chloride ion concentration. All acquired data are timestamped and format standardized, abnormal and redundant data are removed, forming a unified format of raw radioactive waste liquid data set, and a data acquisition completion signal is generated simultaneously.

[0015] Furthermore, the working process of the container security analysis module is as follows:

[0016] Container-related sub-data was extracted from the raw dataset of radioactive waste liquid and labeled as container sub-data. Container sub-data includes internal pressure of the storage tank, tank wall temperature, tank wall thickness, external surface dose rate, radioactivity of leachate from leak monitoring sensors, pH value of the waste liquid, and chloride ion concentration. Pre-stored container safety thresholds from the measurement and monitoring center were retrieved, including the maximum permissible pressure P0 of the storage tank and the safe operating temperature range. Minimum allowable wall thickness t0, maximum allowable dose rate D0 on the outer surface of the tank, background value of radioactivity in leachate Ab, and safe pH range of waste liquid. The maximum permissible concentration of chloride ions, C0, is determined. The obtained container sub-data is then combined with preset container safety thresholds using a formula to analyze and obtain the tank wall corrosion risk value C and the tank wall leakage risk value L. Preset corrosion risk thresholds and leakage risk thresholds are retrieved and analyzed together with the tank wall corrosion risk value C and the tank wall leakage risk value L. If the tank wall corrosion risk value C ≤ the minimum range of the corrosion risk threshold, and the tank wall leakage risk value L ≤ the minimum range of the leakage risk threshold, a container safety signal is generated. If the minimum range of the corrosion risk threshold < the tank wall corrosion risk value C ≤ the maximum range of the corrosion risk threshold, or the minimum range of the leakage risk threshold < the tank wall leakage risk value L ≤ the maximum range of the leakage risk threshold, a container warning signal is generated. If the tank wall corrosion risk value C ≤ the maximum range of the corrosion risk threshold, and the tank wall leakage risk value L ≤ the maximum range of the leakage risk threshold, a container danger signal is generated.

[0017] Furthermore, the working process of the waste liquid sampling risk module is as follows:

[0018] Based on the original dataset of radioactive waste liquid, relevant sub-data of the waste liquid were extracted, including total α activity concentration Aα, total β activity concentration Aβ, characteristic nuclide activity concentration Ai, where i represents different characteristic nuclides, suspended solids content S, and ionic strength I. Historical baseline data pre-stored by the measurement and monitoring center was retrieved, including the total α / total β activity concentration and characteristic nuclide activity concentration of previous samples from the same batch of waste liquid, as well as preset safety thresholds for the waste liquid, such as the total α activity concentration limit Aα0 and the total β activity concentration limit Aβ0. A linear fitting formula was used to obtain the total activity concentration At, and the characteristic nuclide proportion Ri and sampling exposure risk R. 暴露 .

[0019] Furthermore, the safety judgment signal from the container safety analysis module is obtained, combined with preset exposure risk thresholds, total activity trend thresholds, characteristic nuclide thresholds and total activity concentration At, as well as the characteristic nuclide proportion Ri and sampling exposure risk R. 暴露 Conjoint analysis: If the container safety judgment signal is a container safety signal, and the sampling exposure risk R is... 暴露 If the minimum value of the exposure risk threshold is less than or equal to the minimum value of the total activity concentration At, the minimum value of the total activity trend threshold is less than or equal to the minimum value of the characteristic nuclide proportion Ri, then a low-risk signal for waste liquid sampling is generated; if the container safety judgment signal is a container safety signal, and the minimum value of the exposure risk threshold is less than the sampling exposure risk R... 暴露 If the exposure risk is less than or equal to the maximum value of the exposure risk threshold, or if the container safety judgment signal is a container warning signal, then the sampling exposure risk R is considered. 暴露 If the maximum value of the exposure risk threshold > the minimum value of the total activity trend threshold < the total activity concentration At ≤ the maximum value of the total activity trend threshold, then a risk signal for waste liquid sampling is generated; if the container safety judgment signal is a container safety signal, and the sampling exposure risk R 暴露> The maximum value of the exposure risk threshold, or the container safety judgment signal is a container warning signal, and the sampling exposure risk R 暴露 If the total activity concentration At > the maximum value of the container safety judgment signal is greater than the total activity trend threshold, a high-risk signal for waste liquid sampling is generated.

[0020] The beneficial effects of this invention are:

[0021] 1. This invention utilizes a sealed base and sealing gasket, combined with a rotating top plate to create a closed sampling environment. This, along with the linkage between the circulating air pump, air inlet ring, and air exchange port of the gas storage bag frame, efficiently collects radioactive gases overflowing during sampling. This completely avoids the risks of radioactive waste leakage, splashing, and gas diffusion caused by open operations in traditional sampling. The sampling column employs a dual fixing structure of suction cup adsorption and rotating clamp-type locking to ensure safe opening and closing of the sealing cover, preventing the cover from falling off or radioactive material from being exposed during opening. The sampling column precisely controls the sampling depth of the sampling cylinder through screw drive and locking block limitation. Combined with a multi-directional force self-weight sealing structure of the locking cone, this ensures both quantitative control of the sampling volume and prevents waste leakage after sampling, effectively protecting the health of operators and the surrounding ecological environment.

[0022] 2. This invention achieves intelligent risk management and full-process traceability in the sampling process: the multi-source data acquisition module comprehensively covers multi-dimensional data on device operation, container status, and waste liquid characteristics, solving the problem of one-sided data acquisition in traditional sampling; the container safety analysis module generates accurate container safety signals by quantifying tank wall corrosion risk values ​​and leakage risk values, combined with threshold judgment, enabling early identification of container hazards; the waste liquid sampling risk module generates risk level signals by using quantitative analysis such as linear fitting and nuclide ratio calculation, combined with container safety status, avoiding safety accidents caused by blind sampling; the historical data storage and standardized report generation functions of the measurement and monitoring center realize the traceability of sampling data and provide reference guidance for subsequent sampling, improving the standardization level of nuclear facility waste liquid management. Attached Figure Description

[0023] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0024] Figure 1 This is a three-dimensional schematic diagram of the entire invention;

[0025] Figure 2 This is a schematic diagram of the structure of the sealed chassis of the present invention;

[0026] Figure 3 This is a bottom view of the rotating top plate structure of the present invention;

[0027] Figure 4 This is a top view of the rotating top plate of the present invention.

[0028] Figure 5 This is a three-dimensional structural diagram of the cover-removing upright cylinder of the present invention;

[0029] Figure 6 This is a schematic diagram of the internal structure of the sleeve disk of the present invention;

[0030] Figure 7 This is a three-dimensional structural diagram of the sampling column of the present invention;

[0031] Figure 8 This is a schematic diagram of the internal structure of the sampling column of the present invention;

[0032] Figure 9 This is a schematic diagram of the slider of the present invention;

[0033] Figure 10 This is a schematic diagram of the sampling tube of the present invention;

[0034] Figure 11 This is a flowchart of the system of the present invention.

[0035] Attached diagram descriptions: 1. Sealed chassis; 101. Slide rail; 102. Sealing gasket; 103. Air inlet ring; 2. Rotating top plate; 201. Sliding sleeve; 202. Top frame; 203. Air vent; 204. Adapter port; 205. Air storage bag frame; 206. Clip holder; 207. Control pull ring; 3. Sampling column; 301. Back plate; 302. Adapter base pad one; 303. Micro motor; 304. Clip block; 305. Slider; 306. Roller; 307. Lead screw; 308. Slide beam; 309. Limiting locking plate; 310. Pull rod; 311. Locking cone; 312. Sampling cylinder; 4. Capping cylinder; 401. Push rod; 402. Adaptive base pad II; 403. Sleeve disc; 404. Fixing locking rod; 405. Slide rod; 406. Traction wire; 407. Rotating shaft; 408. Rotating clamp; 409. Suction cup. Detailed Implementation

[0036] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0037] Example 1: Please refer to Figure 1 - Figure 11 As shown, this embodiment is a radioactive waste liquid sampling and measuring device and sampling and measuring system, including a sealed base 1, a rotating top plate 2 is provided on the top of the sealed base 1, a top frame 202 and a gas storage bag frame 205 are provided at the center of the top of the rotating top plate 2, a sampling column 3 and a cap-removing cylinder 4 are sleeved on the top frame 202, a push rod 401 is slidably sleeved inside the cap-removing cylinder 4, and a sleeve plate 403 extending into the interior of the sealed base 1 is provided at the bottom of the push rod 401.

[0038] A sealing gasket 102 is embedded in the bottom cross section of the sealed base 1, and an air inlet ring 103 is provided on the inner wall of the bottom of the sealed base 1. A slide rail 101 is provided on the top of the sealed base 1 to cooperate with and connect to the rotating top plate 2. According to the storage tank used to store radioactive waste liquid, the appropriate sleeve plate 403 is replaced according to the model of the storage tank. A certain number of sampling columns 3 are installed in advance according to the sampling measurement needs to complete the preparation of the device. According to the sampling volume required for the sampling measurement, each group of sampling columns 3 is adjusted, and the locking blocks 304 in the long groove are adjusted in sequence. It should be noted that the structure of the device can be made of transparent material or equipped with electronic equipment monitoring according to the usage needs. The electronic equipment monitoring deployment is installed on the inner wall of the rotating top plate 2 to cooperate with the rotating top plate 2 for the storage operation of radioactive waste liquid. It is not limited to this and depends on the actual usage needs of the device.

[0039] The bottom surface of the cover-removing cylinder 4 is provided with an adapter bottom pad 402 that fits into the rotating top plate 2. The top of the sleeve plate 403 is provided with a fixing locking rod 404 that fits into the bottom of the push rod 401. A slide rod 405 is slidably sleeved inside the fixing locking rod 404. A suction cup 409 is provided at the bottom of the slide rod 405. Multiple sets of rotating shafts 407 are arranged in a ring array on the inner wall of the sleeve plate 403. A rotating clamp 408 is hinged on the rotating shaft 407. A traction wire 406 connecting the rotating shaft 407 and the rotating clamp 408 is provided at the top of the slide rod 405.

[0040] Based on the location of the sealing cap on the top of the storage tank, the sealing base plate 1 is placed on top of the storage tank in advance. Due to the external downward pressure and its own weight, the sealing gasket 102 maintains a sealed connection with the top surface of the storage tank. At the same time, the center position of the sealing base plate 1 is adjusted to match the position of the sealing cap, ensuring that the sealing cap is directly below the sleeve plate 403 and the sampling cylinder 312. This step can be performed by positioning and measuring with external auxiliary tools, or by measuring the installation position of the sealing base plate 1 in advance. After the initial installation of the sealing base plate 1 is completed, the rotating top plate 2 is temporarily installed on the sealing base plate 1 through the cooperation of the slide rail 101 and the slide sleeve 201. The top of the air inlet ring 103 is equipped with a valve, which can be connected to the circulating air pump through a pipeline. This completes the construction of a sealed environment between the device and the top of the storage tank. The sealed environment enables the opening and closing of the sealing cap and the storage and retrieval of radioactive waste liquid, effectively avoiding exposure during the opening and closing of radioactive waste liquid and sampling, thus preventing irreversible harm to the surrounding environment and operators.

[0041] Push rod 401 drives sleeve 403 to slide down the sealed interior of cover removal cylinder 4 until sleeve 403 is above the sealing cover. Sleeve 403 slides down until suction cup 409 contacts the top of the sealing cover. With continuous downward pressure, suction cup 409 contacts and squeezes the top of the sealing cover, completing the adsorption and limiting contact between the two. Suction cup 409 is passively pushed upward, and upper sliding rod 405 slides upward along the inside of fixed locking rod 404. Push rod 401 has two sets of upper movable rotating blocks and lower fixed rotating blocks at the top. The bottom of the upper movable rotating block is provided with a traction threaded rod that passes through the lower fixed rotating block, push rod 401, and fixed locking rod 404. The bottom of the traction threaded rod is rotatably sleeved with the top of sliding rod 405. The upper movable rotating block drives the traction threaded rod to rotate synchronously, thereby stretching sliding rod 405 along... The locking rod 404 slides upward inside. After the suction cup 409 abuts against the sealing cover, the movable rotating block rotates back and maintains downward pressure, thereby achieving the covering treatment of the sealing cover by the sleeve 403. During the upward sliding of the suction cup 409, the top of the slide rod 405 drags the traction wire 406 upward synchronously. The traction wire 406 drags the rotating clamp 408 to deflect through the rotating shaft 407. As the sealing cover is gradually put into the sleeve 403, the covering multi-point limiting and locking of the sealing cover is completed. Under the combined action of the externally applied rotational force and continuous downward pressure, the sealing cover is driven to rotate by the push rod 401, sleeve 403, and suction cup 409, thereby achieving the limiting clamping and rotation opening of the sealing cover. The distance between the sealing cover and the opening of the storage tank after limiting is adjusted by adjusting the length of the push rod 401 extending into the sealed environment.

[0042] The rotating top plate 2 is provided with a sliding sleeve 201 at the bottom, and a number of sets of brackets 206 are provided on the outer wall of the top frame 202. The top of the rotating top plate 2 is provided with an adapter port 204 corresponding to each set of brackets 206. The bottom of the air storage bag frame 205 is provided with an air exchange port 203 that penetrates the rotating top plate 2. The top outer wall of the air storage bag frame 205 is provided with a control pull ring 207. The air storage bag frame 205 is provided with a circulating air pump inside, and the circulating air pump is connected to the air exchange port 203 and the air intake ring 103 by pipes.

[0043] Example 2: A back plate 301 is provided on the back of the sampling column 3. A slider 305 is slidably arranged between the sampling column 3 and the back plate 301. A lead screw 307 is embedded inside the front column of the sampling column 3. A sampling cylinder 312 is provided at the bottom of the slider 305. A locking cone 311 is slidably sleeved at the bottom of the sampling cylinder 312. A micro motor 303 is embedded in the top corner of the front of the sampling column 3, which is connected to the lead screw 307 for transmission. A roller 306 is sleeved on the surface of the lead screw 307. The middle of the slider 305 A limiting locking plate 309 is provided through the sampling column 3 to keep engaged with the roller 306. Long grooves are symmetrically provided on both sides of the column, and several sets of holes are provided at equal intervals inside the long grooves. A locking block 304 is provided inside the long groove to engage with the holes. Side blocks are symmetrically provided on both sides of the outer wall of the slider 305. A sliding beam 308 is movably sleeved on the top of the slider 305. A pull rod 310 connected to the locking cone 311 is provided at the bottom of the sliding beam 308. An annular groove is recessed on the bottom inner wall of the sampling cylinder 312.

[0044] By further rotating the top plate 2, the first set of sampling columns 3 is deflected directly above the opening of the storage tank. The micro motor 303 drives the lead screw 307 to rotate via the coupling. The lead screw 307 drives the roller 306 to slide up and down along the inner wall of the sampling column 3. The roller 306 drives the slider 305 to slide vertically down. The slider 305 slides down the inner wall of the sampling column 3 through a side block that slides into a long groove, which limits the up and down sliding of the slider 305. The length of the side block extending into the long groove is less than that of the sliding beam 308. Extending into the long groove, the locking block 304 penetrates the block inside the hole and makes contact with the sliding beam 308. As the slider 305 continues to slide down, it drives the sampling cylinder 312 to slide down synchronously. When the bottom of the sampling cylinder 312 extends into the inside of the storage tank opening, and the slider 305 slides down, causing the sliding beam 308 to contact the locking block 304, the sliding beam 308 is then restricted to its current position. The sliding beam 308 drags the locking cone 311 via the pull rod 310. A drainage groove is provided on the inner wall of the sampling cylinder 312, such as... Figure 10As shown, as the sampling cylinder 312 is submerged inside the radioactive waste liquid, influenced by the liquid pressure inside the storage tank, the radioactive waste liquid flows along the space between the locking cone 311 and the drainage channel and fills the sampling cylinder 312. Sampling is performed based on the depth to which the sampling cylinder 312 is submerged inside the radioactive waste liquid. After sampling is completed, the sampling cylinder 312 slides upwards along with the slider 305, and the slider 308 slides upwards without restriction. Therefore, under the combined influence of the weight of the locking cone 311 and the weight of the radioactive waste liquid inside the sampling cylinder 312, the locking cone 311 is reset to the position of the sampling cylinder 312. At the bottom, the top edge of the locking cone 311 is provided with soft rubber, and the inside of the locking cone 311 is provided with a receiving cavity. Due to the influence of the partial filling of radioactive waste liquid, the soft rubber is caused to tilt outward and adhere to the inner wall of the bottom of the sampling cylinder 312. Combined with the fitting and sleeved connection between the locking cone 311 and the inner wall of the bottom of the sampling cylinder 312, a multi-directional force self-weight sealing structure is realized. In this way, a portion of the radioactive waste liquid collected in the sampling cylinder 312 is sampled and processed quantitatively. The sampling amount is affected by the position of the card block 304 on the sampling column 3 and the amount of radioactive waste liquid stored in the storage tank.

[0045] After sampling of a single storage tank is completed, the top plate 2 is rotated to rotate the cap-retrieving cylinder 4 to directly above the tank opening. The push rod 401 is pushed down again to place the sealing cap held by the upper limit clamp of the sleeve plate 403 onto the tank opening. The upper movable rotating block rotates in the opposite direction, pushing the sealing cap back to fit the tank opening. With the reverse rotation of the push rod 401, the sealing cap and the tank opening are rotated and closed. The circulating air pump inside the gas storage bag frame 205 works in conjunction with the air exchange port 203 and the air inlet ring 103 to first draw air from the top to reduce the internal air pressure of the sealed environment. Then, combined with the air inlet ring 103, air is injected around the bottom of the sealed environment to collect the gas that overflowed during the sampling of the residual radioactive waste liquid inside the sealed environment into the gas storage bag frame 205. After this step is completed, the whole device is disassembled according to the sampling and measurement needs, and each set of sampling columns 3 is marked and disassembled separately, waiting for subsequent sampling and testing of the radioactive waste liquid inside the sampling cylinder 312.

[0046] Example 3: A radioactive waste liquid sampling and measurement device and sampling and measurement system, including a measurement monitoring center, a multi-source measurement data acquisition module, a container safety analysis module, and a waste liquid sampling risk module. Each module achieves bidirectional communication through a data transmission link.

[0047] The multi-source data acquisition module collects raw data from radioactive waste liquid and storage tanks and transmits it to the container safety analysis module and the measurement monitoring center. The working process of the multi-source data acquisition module is as follows:

[0048] Based on the sampling and measurement device installed on the storage tank to create a sealed environment, combined with the sensors deployed in the sampling and measurement device, the operating range is defined to determine the data acquisition range and obtain the sampling device operation data, storage tank status data, and radioactive waste liquid characteristic data. The corresponding data are obtained through the sensors deployed on the sampling and measurement device or storage tank, such as the radioactive detector built into the sampling tube, the sealed environment pressure sensor, as well as the tank wall temperature sensor, ultrasonic thickness gauge, and leakage monitoring sensor.

[0049] Real-time acquisition of sampling device operation data, including sealed environment air pressure, sampling depth of sampling tube, and locking cone sealing pressure;

[0050] Real-time acquisition of storage tank status data, including internal pressure, tank wall temperature, tank wall thickness, external surface dose rate, and leachate radioactivity levels from leak monitoring sensors;

[0051] Real-time acquisition of radioactive waste liquid characteristic data, including total alpha activity concentration, total beta activity concentration, characteristic nuclide activity concentration, waste liquid pH value, suspended solids content, and chloride ion concentration. The characteristic nuclide activity concentration covers one or more of cobalt-60, cesium-137, and uranium-238, depending on the radioactive waste liquid in the current storage tank.

[0052] All collected data are timestamped and standardized in format, and abnormal and redundant data are removed to form a unified set of raw data for radioactive waste liquid. At the same time, a data collection completion signal is generated. After receiving the signal, the measurement and monitoring center triggers the container safety analysis module to start. Staff can view the details of the raw data through the measurement and monitoring center and check for abnormal data collection.

[0053] The container safety analysis module performs joint analysis on container-related sub-data in the raw data to generate a container safety judgment signal, which is then synchronously transmitted to the waste liquid sampling risk module and the measurement and monitoring center. The working process of the container safety analysis module is as follows:

[0054] Container-related sub-data was extracted from the raw dataset of radioactive waste liquid and labeled as container sub-data. Container sub-data includes internal pressure of the storage tank, tank wall temperature, tank wall thickness, external surface dose rate, radioactivity of leachate from leak monitoring sensors, pH value of the waste liquid, and chloride ion concentration. Pre-stored container safety thresholds from the measurement and monitoring center were retrieved, including the maximum permissible pressure P0 of the storage tank and the safe operating temperature range. Minimum allowable wall thickness t0, maximum allowable dose rate D0 on the outer surface of the tank, background value of radioactivity in leachate Ab, and safe pH range of waste liquid. The maximum permissible concentration of chloride ions, C0;

[0055] The obtained container sub-data is combined with the container safety preset threshold and analyzed using formulas to obtain the tank wall corrosion risk value C and the tank wall leakage risk value L:

[0056] By normalizing the degree of pH deviation from neutrality and the degree of chloride ion concentration exceeding the standard, and then weighting and summing them according to weighting coefficients, the impact of corrosion on the container and the risk value of tank wall corrosion are quantified. ,in, , Represented as weighting coefficients, =0.6, =0.4, which satisfies + =1, Indicated as actual measurement of waste liquid value, This is expressed as the measured chloride ion concentration in the waste liquid. It is expressed as the absolute value of the difference between the measured pH value of the waste liquid and the neutral pH value. The neutral pH value of 7 is the standard for neutrality of aqueous solution.

[0057] By normalizing the degree of dose rate exceeding the standard on the tank's outer surface and the degree of radioactivity exceeding the background level in the leachate, and then weighting and summing them according to weighting coefficients, the leakage risk is quantified, resulting in the tank wall leakage risk value. ,in, , Represented as weighting coefficients, =0.7, =0.3, which satisfies + =1, This is expressed as the measured dose rate value on the outer surface of the canister. This is expressed as the measured radioactivity value of the leachate;

[0058] Determine the pressure and temperature status of the storage tank: >P0 or Not equal to If so, it is marked as a pressure / temperature anomaly;

[0059] If the thickness is less than T0, it is marked as insufficient wall thickness;

[0060] Retrieve preset corrosion risk thresholds and leakage risk thresholds, and perform joint analysis with tank wall corrosion risk value C and tank wall leakage risk value L:

[0061] If the tank wall corrosion risk value C ≤ the minimum range of the corrosion risk threshold, and the tank wall leakage risk value L ≤ the minimum range of the leakage risk threshold, then a container safety signal is generated. The container safety signal indicates that the container is currently structurally intact, and the risk of corrosion and leakage is extremely low, so sampling operations can be carried out normally.

[0062] If the minimum range of corrosion risk threshold < tank wall corrosion risk value C ≤ the maximum range of corrosion risk threshold, or the minimum range of leakage risk threshold < tank wall leakage risk value L ≤ the maximum range of leakage risk threshold, a container warning signal is generated. The container warning signal indicates that the container has slight corrosion or potential leakage risk, or that key parameters are slightly out of standard, and the monitoring frequency needs to be increased before sampling.

[0063] If the tank wall corrosion risk value C is less than or equal to the maximum range of the corrosion risk threshold, and the tank wall leakage risk value L is less than or equal to the maximum range of the leakage risk threshold, a container hazard signal is generated. The container hazard signal indicates that the container has serious corrosion, leakage risk, or insufficient structural strength. The sampling process may cause serious hazards such as container rupture and waste liquid leakage.

[0064] The waste liquid sampling risk module combines waste liquid-related sub-data from the original data with container safety judgment signals. Through data comparison, conversion, and analysis, it generates a waste liquid sampling safety signal, which is then transmitted to the measurement and monitoring center. The working process of the waste liquid sampling risk module is as follows:

[0065] Based on the original dataset of radioactive waste liquid, relevant sub-data of waste liquid were extracted, including total α activity concentration Aα, total β activity concentration Aβ, characteristic nuclide activity concentration Ai, waste liquid suspended solids content S, and waste liquid ionic strength I. In the characteristic nuclide activity concentration Ai, i represents different characteristic nuclides.

[0066] Historical baseline data and preset safety thresholds for waste liquid were retrieved from the measurement and monitoring center. Historical baseline data included the total α / total β activity concentration and characteristic nuclide activity concentration from previous samples of the same batch of waste liquid. Preset safety thresholds for waste liquid were represented as the total α activity concentration limit Aα0 and the total β activity concentration limit Aβ0. A linear fitting formula was used to obtain the total activity concentration At, the characteristic nuclide proportion Ri, and the sampling exposure risk R. 暴露 :

[0067] By using linear fitting, discrete historical data and current data are transformed into a trend equation. The slope 'a' reflects the rate of activity change. 'a > 0' represents an increase in activity, and 'a < 0' represents a decrease in activity. The total activity concentration At = a × t + b, where t represents the sampling time, a represents the trend slope of the rate of activity change, and b represents the intercept. By fitting historical data with current measured data, the trend of total activity concentration is determined.

[0068] The influence weight of high-risk nuclides and the proportion of characteristic nuclides are determined by the ratio of the activity of a single characteristic nuclide to the total α+ and total β activities. Calculate the proportion of each characteristic nuclide in the total activity;

[0069] The risk of radioactive exposure and nuclide migration during sampling was quantified by weighting and summing the total activity exceedance, suspended solids content, and ionic strength according to their respective weights. Among them, exposure risk This represents the combined risk of radioactive exposure and nuclide migration during the quantitative sampling process; the higher the value, the greater the risk. , and Represented as weighting coefficients, =0.5, =0.3, =0.2, which satisfies + + =1, Expressed as the total α and total β activity concentration limits, Expressed as the measured total alpha activity concentration in the waste liquid, it refers to the measured value of the total activity concentration of all alpha radionuclides in the waste liquid extracted from the original data of the radioactive waste liquid. Expressed as the measured total β activity concentration in the waste liquid, it refers to the measured value of the total activity concentration of all β radionuclides in the waste liquid extracted from the original data of the radioactive waste liquid. This is expressed as the total alpha activity concentration limit, which is the safe threshold for the total alpha activity concentration of waste liquid that meets relevant national standards and is pre-stored by the measurement and monitoring center. It is expressed as the total β activity concentration limit, which is the safe threshold for the total β activity concentration of waste liquid that meets the relevant national standards and is pre-stored by the measurement and monitoring center.

[0070] The safety judgment signal from the container safety analysis module is obtained, and combined with preset exposure risk thresholds, total activity trend thresholds, characteristic nuclide thresholds and total activity concentration At, as well as the characteristic nuclide proportion Ri and sampling exposure risk R. 暴露 Joint analysis:

[0071] If the container safety assessment signal is a container safety signal, and the sampling exposure risk R 暴露 If the minimum value of the exposure risk threshold, the minimum value of the total activity concentration At, and the minimum value of the total activity trend threshold, are all specified, and the minimum value of the characteristic nuclide proportion Ri, then a low-risk signal for waste liquid sampling is generated. A low-risk signal for waste liquid sampling indicates that the radioactivity level of the waste liquid is compliant, the activity is stable, the container is safe, the sampling process has extremely low risk, and sampling can be carried out according to the conventional procedure. The staff operates the sampling device according to the conventional procedure to complete the sampling.

[0072] If the container safety assessment signal is a container safety signal, and the minimum exposure risk threshold is less than the sampling exposure risk R... 暴露 If the exposure risk is less than or equal to the maximum value of the exposure risk threshold, or if the container safety judgment signal is a container warning signal, then the sampling exposure risk R is considered. 暴露If the maximum value of the exposure risk threshold > the minimum value of the total activity trend threshold < the total activity concentration At ≤ the maximum value of the total activity trend threshold, then a risk signal in waste liquid sampling is generated. A risk signal in waste liquid sampling indicates that the radioactivity level of the waste liquid is close to the limit or the activity has increased slightly, or the container has a slight warning. Enhanced protection measures need to be taken during the sampling process. The measurement and monitoring center pushes an enhanced protection reminder, the sampling device automatically shortens the sampling dwell time, and the sampling is started after the staff confirms that the protection is in place.

[0073] If the container safety assessment signal is a container safety signal, and the sampling exposure risk R 暴露 > The maximum value of the exposure risk threshold, or the container safety judgment signal is a container warning signal, and the sampling exposure risk R 暴露 If the total activity concentration At > the exposure risk threshold range, or if the container safety judgment signal is the maximum value of the container hazard signal total activity concentration At > the total activity trend threshold, a high-risk signal for waste liquid sampling is generated. A high-risk signal for waste liquid sampling indicates that the radioactivity level of the waste liquid is seriously exceeded, the activity is rising rapidly, or the container has a high safety risk. The sampling process may lead to serious radioactive leakage, excessive exposure of staff, and other hazards. The measurement and monitoring center will immediately trigger an audible and visual alarm, prohibit the sampling device from starting sampling, and staff must suspend sampling and develop a special handling plan.

[0074] The measurement and monitoring center summarizes the received signals to generate a complete sampling report, receives and stores the original data set of radioactive waste liquid transmitted by the multi-source data acquisition module, the container safety judgment signal transmitted by the container safety analysis module, and the waste liquid sampling safety signal transmitted by the waste liquid sampling risk module, and associates the corresponding timestamps, sampling device numbers, and storage tank numbers to establish a traceable data archive.

[0075] Retrieve pre-stored historical data archives and compare the current raw data of radioactive waste liquid with historical data of storage tanks with the same number and the same type of waste liquid to analyze the consistency of data change trends;

[0076] Based on a preset report generation template, the system integrates raw data details, container safety assessment results, waste liquid sampling risk levels, and historical data comparison results to generate a complete sampling report containing basic sampling information, data collection details, safety analysis conclusions, risk assessment results, and operational recommendations. The complete sampling report indicates that all sampling and measurement data has been analyzed and integrated to form a standardized report that can be used for subsequent processing. Push notifications corresponding to different risk levels represent the safety status of the sampling process and the necessary countermeasures.

[0077] The corresponding operation is triggered based on the waste liquid sampling safety signal:

[0078] If the waste liquid sampling is a low-risk signal, only a sampling report will be generated and stored; if the waste liquid sampling is a medium-risk signal, a sampling report will be generated and an enhanced protection prompt will be pushed to the staff's terminal.

[0079] If a high-risk signal is detected for waste liquid sampling, a sampling report will be generated, an emergency alarm will be triggered, and the signal will be simultaneously pushed to the safety management terminal.

[0080] Sampling reports and alarm records (if any) will be stored long-term, and historical data archives will be updated to provide a reference baseline for subsequent sampling of similar waste liquids.

[0081] The above description is merely an example and illustration of the structure of the present invention. Those skilled in the art can make various modifications or additions to the specific embodiments described, or use similar methods to replace them, as long as they do not deviate from the structure of the invention or exceed the scope defined in the claims, all of which should fall within the protection scope of the present invention.

[0082] In the description of this specification, references to terms such as "an embodiment," "example," "specific example," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the invention. In this specification, illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples.

[0083] The preferred embodiments of the present invention disclosed above are merely illustrative of the invention. These preferred embodiments do not exhaustively describe all details, nor do they limit the invention to any specific implementation. Clearly, many modifications and variations can be made based on the content of this specification. This specification selects and specifically describes these embodiments to better explain the principles and practical applications of the invention, thereby enabling those skilled in the art to better understand and utilize the invention. The invention is limited only by the claims and their full scope and equivalents.

Claims

1. A radioactive waste liquid sampling and measuring device, comprising a sealed chassis (1), characterized in that, The top of the sealed chassis (1) is provided with a rotating top plate (2), and the top center of the rotating top plate (2) is provided with a top frame (202) and an air storage bag frame (205). The top frame (202) is sleeved with a sampling column (3) and a cap removal cylinder (4). The cap removal cylinder (4) is slidably sleeved with a push rod (401) inside. The bottom of the push rod (401) is provided with a sleeve plate (403) extending into the interior of the sealed chassis (1). The sampling column (3) has a back plate (301) on its back side. A slider (305) is slidably arranged between the sampling column (3) and the back plate (301). A lead screw (307) is embedded in the front column of the sampling column (3). A sampling cylinder (312) is provided at the bottom of the slider (305). A locking cone (311) is slidably sleeved at the bottom of the sampling cylinder (312).

2. The radioactive waste liquid sampling and measuring device according to claim 1, characterized in that, A sealing gasket (102) is embedded on the bottom cross section of the sealing chassis (1), an air intake ring (103) is provided on the bottom inner wall of the sealing chassis (1), and a slide rail (101) is provided on the top of the sealing chassis (1) to cooperate with and connect with the rotating top plate (2).

3. The radioactive waste liquid sampling and measuring device according to claim 1, characterized in that, The rotating top plate (2) is provided with a sliding sleeve (201) at the bottom, and a number of card holders (206) are provided on the outer wall of the top frame (202). The rotating top plate (2) is provided with an adapter port (204) corresponding to each card holder (206) through the top. The air storage bag frame (205) is provided with an air exchange port (203) through the rotating top plate (2) at the bottom. The air storage bag frame (205) is provided with a control pull ring (207) on the top outer wall.

4. The radioactive waste liquid sampling and measuring device according to claim 1, characterized in that, The bottom surface of the cover-removing cylinder (4) is provided with a matching bottom pad (402) that fits into the rotating top plate (2). The top of the sleeve plate (403) is provided with a fixed locking rod (404) that fits into the bottom of the push rod (401). A sliding rod (405) is slidably fitted inside the fixed locking rod (404). A suction cup (409) is provided at the bottom of the sliding rod (405). Multiple sets of rotating shafts (407) are arranged in a ring array on the inner wall of the sleeve plate (403). A rotating clamp (408) is hinged on the rotating shaft (407). A traction wire (406) connecting the rotating shaft (407) and the rotating clamp (408) is provided at the top of the sliding rod (405).

5. The radioactive waste liquid sampling and measuring device according to claim 1, characterized in that, The sampling column (3) has a micro motor (303) embedded in one corner of the front top, which is connected to the lead screw (307) for transmission. The lead screw (307) is fitted with a roller (306). The slider (305) has a limiting locking plate (309) that is engaged with the roller (306) through the middle. The two sides of the sampling column (3) have long grooves symmetrically arranged, and several sets of holes are evenly spaced inside the long grooves. The long grooves have locking blocks (304) that are engaged with the holes. The two sides of the slider (305) have side blocks symmetrically arranged. The top of the slider (305) is movably fitted with a sliding beam (308). The bottom of the sliding beam (308) is provided with a pull rod (310) connected to the locking cone (311). The bottom inner wall of the sampling cylinder (312) is recessed with an annular groove. The bottom of the sampling column (3) is provided with an adapter bottom pad (302) that is connected to the rotating top plate (2).

6. A radioactive waste liquid sampling and measurement system, used in the radioactive waste liquid sampling and measurement device according to any one of claims 1-5, characterized in that, The system includes a measurement and monitoring center, a multi-source measurement data acquisition module, a container safety analysis module, and a waste liquid sampling risk module. Each module communicates bidirectionally via a data transmission link. The multi-source measurement data acquisition module collects raw data from radioactive waste liquid and storage tanks and transmits it to the container safety analysis module and the measurement and monitoring center. The container safety analysis module performs joint analysis on container-related sub-data in the raw data to generate a container safety judgment signal, which is simultaneously transmitted to the waste liquid sampling risk module and the measurement and monitoring center. The waste liquid sampling risk module combines waste liquid-related sub-data from the raw data with the container safety judgment signal, performs data comparison and conversion analysis to generate a waste liquid sampling safety signal, which is transmitted to the measurement and monitoring center. The measurement and monitoring center summarizes the received signals to generate a complete sampling report.

7. The radioactive waste liquid sampling and measurement system according to claim 6, characterized in that, The working process of the multi-source data acquisition module is as follows: Based on the sealed environment constructed by installing the sampling and measurement device on the storage tank, and combined with the sensors deployed inside the sampling and measurement device, the data acquisition range is defined by its operating range, and the operating data of the sampling device, the status data of the storage tank, and the characteristic data of the radioactive waste liquid are obtained. All the collected data are timestamped and format standardized, abnormal and redundant data are removed, and a set of raw data of radioactive waste liquid in a unified format is formed. At the same time, a data acquisition completion signal is generated.

8. The radioactive waste liquid sampling and measurement system according to claim 7, characterized in that, The working process of the container security analysis module is as follows: Extract container-related sub-data from the original dataset of radioactive waste liquid and mark it as container sub-data; retrieve the container safety preset thresholds stored in the measurement and monitoring center, and combine the obtained container sub-data with the container safety preset thresholds to obtain the tank wall corrosion risk value C and the tank wall leakage risk value L. Retrieve the preset corrosion risk threshold and leakage risk threshold and analyze them together with the tank wall corrosion risk value C and the tank wall leakage risk value L: if the tank wall corrosion risk value C ≤ the minimum range of the corrosion risk threshold and the tank wall leakage risk value L ≤ the minimum range of the leakage risk threshold, then a container safety signal is generated; if the minimum range of the corrosion risk threshold < the tank wall corrosion risk value C ≤ the maximum range of the corrosion risk threshold, or the minimum range of the leakage risk threshold < the tank wall leakage risk value L ≤ the maximum range of the leakage risk threshold, then a container warning signal is generated. If the tank wall corrosion risk value C is less than or equal to the maximum range of the corrosion risk threshold, and the tank wall leakage risk value L is less than or equal to the maximum range of the leakage risk threshold, then a container hazard signal is generated.

9. A radioactive waste liquid sampling and measurement system according to claim 8, characterized in that, The working process of the waste liquid sampling risk module is as follows: Based on the original dataset of radioactive waste liquid, relevant sub-data of the waste liquid were extracted, including total α activity concentration Aα, total β activity concentration Aβ, characteristic nuclide activity concentration Ai, suspended solids content S, and ionic strength I. Historical baseline data pre-stored by the measurement and monitoring center was retrieved, including the total α / total β activity concentration and characteristic nuclide activity concentration of previous samples from the same batch of waste liquid, as well as preset safety thresholds for the waste liquid, such as the total α activity concentration limit Aα0 and the total β activity concentration limit Aβ0. A linear fitting formula was used to obtain the total activity concentration At, and the characteristic nuclide proportion Ri and sampling exposure risk R. 暴露 .

10. A radioactive waste liquid sampling and measurement system according to claim 9, characterized in that, The safety judgment signal from the container safety analysis module is obtained, and combined with preset exposure risk thresholds, total activity trend thresholds, characteristic nuclide thresholds and total activity concentration At, as well as the characteristic nuclide proportion Ri and sampling exposure risk R. 暴露 Conjoint analysis: If the container safety judgment signal is a container safety signal, and the sampling exposure risk R is... 暴露 If the minimum value of the exposure risk threshold, the minimum value of the total activity concentration At, and the minimum value of the total activity trend threshold, are all specified, and the minimum value of the characteristic nuclide proportion Ri, then a low-risk signal for waste liquid sampling is generated. If the container safety assessment signal is a container safety signal, and the minimum exposure risk threshold is less than the sampling exposure risk R... 暴露 If the exposure risk is less than or equal to the maximum value of the exposure risk threshold, or if the container safety judgment signal is a container warning signal, then the sampling exposure risk R is considered. 暴露 If the maximum value of the exposure risk threshold > the minimum value of the total activity trend threshold < the total activity concentration At ≤ the maximum value of the total activity trend threshold, then a risk signal is generated in waste liquid sampling. If the container safety assessment signal is a container safety signal, and the sampling exposure risk R 暴露 > The maximum value of the exposure risk threshold, or the container safety judgment signal is a container warning signal, and the sampling exposure risk R 暴露 If the total activity concentration At > the maximum value of the container safety judgment signal is greater than the total activity trend threshold, a high-risk signal for waste liquid sampling is generated.

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