CN117309833A - Portable rapid uranium detection system and method - Google Patents
Portable rapid uranium detection system and method Download PDFInfo
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/62—Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light
- G01N21/63—Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light optically excited
- G01N21/64—Fluorescence; Phosphorescence
- G01N21/6428—Measuring fluorescence of fluorescent products of reactions or of fluorochrome labelled reactive substances, e.g. measuring quenching effects, using measuring "optrodes"
- G01N21/643—Measuring fluorescence of fluorescent products of reactions or of fluorochrome labelled reactive substances, e.g. measuring quenching effects, using measuring "optrodes" non-biological material
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/01—Arrangements or apparatus for facilitating the optical investigation
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/62—Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light
- G01N21/63—Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light optically excited
- G01N21/64—Fluorescence; Phosphorescence
- G01N21/645—Specially adapted constructive features of fluorimeters
- G01N21/6456—Spatial resolved fluorescence measurements; Imaging
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- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/01—Arrangements or apparatus for facilitating the optical investigation
- G01N2021/0106—General arrangement of respective parts
- G01N2021/0112—Apparatus in one mechanical, optical or electronic block
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a portable rapid uranium detection system and a method, and relates to the technical field of element detection. The portable rapid uranium detection system provided by the invention can be used for rapidly detecting the radioactive element uranium.
Description
Technical Field
The invention relates to the technical field of element detection, in particular to a portable rapid detection system and method for uranium.
Background
Uranium is an important radioactive element, and long-term exposure thereof causes serious harm to human health and natural environment. The pollution source of uranium can be timely found and controlled by realizing on-line detection and portable detection of uranium element, and environmental protection and health risk management are facilitated. Uranium has wide application in the nuclear energy field, but is also a key factor in nuclear security management. The on-line detection and the portable detection of uranium elements are realized, and the on-line detection and the portable detection can be used for carrying out real-time monitoring and rapid response on nuclear energy related areas such as nuclear power plants, nuclear factories and the like, so that accidents are prevented, and nuclear safety is ensured. Uranium is one of important mineral resources, so that the sampling efficiency of a mine can be improved by realizing portable detection, and the content of uranium in the mine and the like can be monitored in real time by realizing on-line detection, so that data support is provided for mineral resource management, and more efficient and sustainable mineral resource development is promoted. The uranium element online detection and portable detection technology not only has application in the fields of nuclear energy, environmental protection, mineral resources and the like, but also can be applied to other fields of water quality monitoring, medical diagnosis and the like, and provides data support for related fields. Realizes the on-line detection and the portable detection of uranium element, is beneficial to guaranteeing the health and the environmental safety of human beings, promotes the development and the sustainable development of mineral resources, and is a research field with wide application prospect and important significance.
The existing uranium measurement method mainly comprises a physical measurement method and a chemical measurement method. The physical measurement method is to obtain uranium content information by measuring physical properties such as particle detection, gamma ray detection and the like of a uranium sample. Common physical measurement methods include alpha/beta counting, neutron activation analysis, and spectroscopy. The chemical measurement method is to separate uranium by adopting chemical reaction of uranium and other elements, and quantitatively measure uranium by using the chemical method. Common chemical measurement methods include extraction, colorimetry, titration, and the like. Among them, colorimetry is currently the most commonly used method: the method comprises the steps of carrying out chemical reaction on uranium in a sample and an indicator to generate a complex with color, measuring the color intensity of the complex, and measuring the uranium content according to the linear relation between the concentration and the absorbance. The main defects of colorimetric uranium measurement are low selectivity and sensitivity, and the measurement process requires a spectrophotometer and is inconvenient for field measurement.
Disclosure of Invention
The invention aims to provide a portable rapid uranium detection system and method, which can be used for rapidly detecting radioactive element uranium.
In order to achieve the above object, the present invention provides the following solutions:
the invention provides a portable rapid uranium detection system which can be used in combination with a radionuclide automatic separation device, wherein the radionuclide automatic separation device is used for carrying out matrix separation and enrichment of target uranium to obtain a solution to be detected, the portable rapid uranium detection system comprises an upper computer, a detection chamber, a colorimetric test tube, an optical signal acquisition module and a light source module, the colorimetric test tube is used for containing the solution to be detected and fluorescent reagent, the colorimetric test tube is a disposable plastic test tube, the colorimetric test tube is placed in the detection chamber, the light source module outputs an optical signal to irradiate on the colorimetric test tube, the fluorescent reagent in the colorimetric test tube generates a fluorescent signal after excitation of the light source module, the fluorescent signal returns to the colorimetric test tube and is acquired by the optical signal acquisition module, and the optical signal acquisition module is connected with the upper computer;
the upper computer is used for determining the uranium concentration in the solution to be detected according to the fluorescent signal image of the solution to be detected, which is acquired by the optical signal acquisition module.
Preferably, the optical signal acquisition module is arranged on one side of the colorimetric tube, and the light source module is arranged above the colorimetric tube or below the colorimetric tube.
Preferably, the detection chamber is provided with a first light path, the first light path coincides with the axis of the colorimetric tube, the light signal output by the light source module is transmitted to the colorimetric tube through the first light path, and the fluorescent signal generated by excitation of the fluorescent reagent in the colorimetric tube through the light source module returns to the colorimetric tube through the first light path; the detection chamber is provided with a second light path, the second light path is perpendicular to the axis of the colorimetric tube, and the fluorescent signal returned to the colorimetric tube is conveyed to the light signal acquisition module through the second light path.
Preferably, the light source module comprises an ultraviolet light LED chip, a supporting structure, a heat sink and a fan, wherein the ultraviolet light LED chip is arranged on the supporting structure, one end of the heat sink is connected with the supporting structure, and the other end of the heat sink is provided with the fan.
Preferably, a filter is arranged between the light source module and the colorimetric tube.
Preferably, the optical signal acquisition module is a camera.
The invention also provides a portable rapid uranium detection method, which is applied to the portable rapid uranium detection system, and comprises the following steps:
acquiring a fluorescence signal image of a solution to be detected; the fluorescence signal of the solution to be detected is generated through excitation of the light source module, and the fluorescence signal image is acquired through the light signal acquisition module;
extracting an R channel information value, a G channel information value and a B channel information value of the fluorescent signal image;
according to the B channel information value, determining a uranium concentration measurement value in the solution to be detected by utilizing a B channel standard working curve; the standard working curve of the B channel is determined according to the concentration of the standard solution and the information value of the B channel of the standard solution;
according to the R channel information value, determining a first reference value of uranium concentration in the solution to be detected by utilizing an R channel standard working curve; the R channel standard working curve is determined according to the concentration of the standard solution and the R channel information value of the standard solution;
according to the G channel information value, determining a second reference value of uranium concentration in the solution to be detected by utilizing a G channel standard working curve; the standard working curve of the G channel is determined according to the concentration of the standard solution and the G channel information value of the standard solution;
and carrying out error correction on the uranium concentration measured value in the solution to be detected according to the uranium concentration first reference value and the uranium concentration second reference value.
Compared with the prior art, the invention has the following technical effects:
the invention can rapidly complete the detection and analysis of the radioactive element uranium, has the advantages of simplicity, reliability and high efficiency, and greatly enhances the upgradeability and portability of the device due to the modularized design. The invention can be combined with the radionuclide automatic separation device to realize automatic stay detection, so that the complex steps of manual operation and measurement are avoided, the labor intensity of personnel is greatly reduced, and meanwhile, the safety of analysis personnel can be greatly improved due to the minimal contact with aggressive acid and the remote operation of radioactive samples.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are needed in the embodiments will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is an isometric view of the positional relationship among a detection chamber, a colorimetric tube, an optical signal acquisition module and a light source module of the present invention;
FIG. 2 is a front view of FIG. 1;
FIG. 3 is an isometric view of a test chamber of the present invention;
FIG. 4 is a bottom view of the detection chamber of the present invention;
FIG. 5 is a second perspective view of the detection chamber of the present invention;
FIG. 6 is a bottom view of a second detection chamber of the present invention;
FIG. 7 is an isometric view of a light source module of the present invention;
FIG. 8 is a bottom view of the light source module of the present invention;
FIG. 9 is a block diagram of a portable rapid detection system for uranium according to the present invention;
FIG. 10 is a schematic circuit diagram of a circuit driving module according to the present invention;
FIG. 11 is a flow chart of a portable rapid detection method of uranium according to the present invention;
FIG. 12 is a schematic diagram of a standard working curve of the B-channel of the present invention.
Wherein: the device comprises a 1-detection chamber, a 2-colorimetric test tube, a 3-optical signal acquisition module, a 4-light source module, a 5-ultraviolet LED chip, a 6-supporting structure, a 7-radiating fin, an 8-fan, a 9-upper computer, a 10-circuit system and an 11-signal processing module.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by a person skilled in the art based on the embodiments of the invention without any inventive effort, are intended to fall within the scope of the invention.
The invention aims to provide a portable rapid uranium detection system and method, which can be used for rapidly detecting radioactive element uranium.
In order that the above-recited objects, features and advantages of the present invention will become more readily apparent, a more particular description of the invention will be rendered by reference to the appended drawings and appended detailed description.
Embodiment one:
as shown in fig. 1 to 9: the embodiment provides a portable rapid uranium detection system, which can be combined with a radionuclide automatic separation device, wherein the radionuclide automatic separation device is used for separating matrixes and enriching target uranium to obtain a solution to be detected, the portable rapid uranium detection system comprises an upper computer 9, a detection chamber 1, a colorimetric test tube 2, an optical signal acquisition module 3 and a light source module 4, the colorimetric test tube 2 is used for containing the solution to be detected and a fluorescent reagent, the colorimetric test tube 2 is a disposable plastic test tube, the colorimetric test tube 2 is placed in the detection chamber 1, the light source module 4 outputs an optical signal to irradiate on the colorimetric test tube 2, the fluorescent reagent in the colorimetric test tube 2 generates a fluorescent signal through excitation of the light source module 4, the fluorescent signal returns to the colorimetric test tube 2 and is acquired by the optical signal acquisition module 3, and the optical signal acquisition module 3 is electrically connected with the upper computer 9;
the upper computer 9 is used for determining the uranium concentration in the solution to be detected according to the fluorescent signal image of the solution to be detected, which is acquired by the optical signal acquisition module.
Specifically, in this embodiment, the upper computer 9 is a single-chip microcomputer, a PC or a mobile smart phone. The power supply module (circuit system 10) of the portable rapid uranium detection system of the embodiment can directly use the upper computer 9 to supply power through a data line, and can also use a developed program to perform visual operation, so that the portable rapid uranium detection system has obvious advantages; alternatively, circuitry 10 may use a portable battery to power light source module 4.
In this embodiment, the optical signal acquisition module 3 is preferably an FS02T1 type ultra-clear 1080p camera, the optical signal acquisition module 3 is disposed on one side of the cuvette 2, and the optical signal acquisition module 3 includes a receiver, which can accurately acquire a signal and convert the signal into a digital signal, and meanwhile, a reflected optical signal in the cuvette 2 is also received and acquired into the optical signal acquisition module 3 for storage and transmission.
In this embodiment, the detection chamber 1 is provided with a first optical path, the first optical path coincides with the axis of the cuvette 2, the optical signal output by the light source module 4 is conveyed to the cuvette 2 through the first optical path, and the fluorescent signal generated by the excitation of the fluorescent reagent in the cuvette 2 by the light source module 4 returns to the cuvette 2 through the first optical path.
In this embodiment, the detection chamber 1 is provided with a second optical path perpendicular to the axis of the cuvette 2, and the fluorescent signal returned to the cuvette 2 is transmitted to the optical signal acquisition module 3 through the second optical path. The second optical path may be provided in plurality as necessary.
The detection chamber 1 in this embodiment is manufactured by using a 3D printing technology, and can be quickly matched with different optical signal acquisition modules 3 at low cost.
In this embodiment, the light source module 4 is located above the cuvette 2 or below the cuvette 2, the light source module 4 includes an ultraviolet LED chip 5, a supporting structure 6, a heat sink 7 and a fan 8, the ultraviolet LED chip 5 can convert electric energy into ultraviolet energy, a filter is disposed between the ultraviolet LED chip 5 and the cuvette 2, the filter is used for selecting and limiting a wavelength range output by the light source, and sending light in the selected wavelength range into the detection chamber 1, so that excessive light can be effectively prevented from entering the detection chamber 1, the signal-to-noise ratio and the detection precision are improved, the ultraviolet LED chip 5 is packaged by a packaging structure to improve heat resistance and humidity resistance, the packaging structure adopts a transparent material such as epoxy resin or silica gel, the packaged ultraviolet LED chip 5 is disposed on the supporting structure 6, the supporting structure 6 can be a metal or ceramic substrate for providing mechanical strength and enhancing heat dissipation, one end of the heat sink 7 is connected with the supporting structure 6, and the fan 8 is disposed at the other end of the heat sink 7. The structure of the radiating fin 7 and the fan 8 effectively radiates heat generated by the ultraviolet LED chip 5 during working, prevents the ultraviolet LED chip 5 from overheating, and ensures the long-term stability of the light source module 4.
In this embodiment, the light source module 4 further includes a circuit driving module, which generally includes a dc power supply, a current regulator, a protection circuit, and the like, and is connected to the uv LED chip 5 for providing appropriate voltage and current to ensure the normal operation and protection of the uv LED chip 5. As shown IN fig. 10, a first end of a 10K ohm resistor R1 is connected to a 12V power supply, a second end of the 10K ohm resistor R1 is grounded, and a third end of the 10K ohm resistor R1 is connected to a-IN pin of U1A; the first end of the 10K ohm resistor R4 is connected with a 12V power supply, the second end of the 10K ohm resistor R4 is grounded, and the third end of the 10K ohm resistor R4 is connected to the +IN pin of the U1B. A first end of the 1K ohm resistor R2 is connected to an OUT pin of the U1A, and a second end of the 1K ohm resistor R2 is connected to a base electrode of the transistor Q1; a first terminal of the 1K ohm resistor R3 is connected to the OUT pin of U1B and a second terminal of the 1K ohm resistor R3 is connected to the base of transistor Q2.
The emitter of the transistor Q1 is connected to GND and the base is connected to R2. The emitter of the transistor Q2 is connected to GND and the base is connected to R3.
The input signal is connected to the +IN pin of U1A and the-IN pin of U1B.
The input signal is amplified by the operational amplifiers of U1A and U1B.
Ohmic resistor R2 and ohmic resistor R3 are connected to the output pins of U1A and U1B, and the magnitude of the current is controlled by adjusting the resistance value.
The anode of the ultraviolet LED chip 5 is connected to the collector of the transistor Q1, and the cathode of the ultraviolet LED chip 5 is connected to the collector of the transistor Q2.
The transistor Q1 and the transistor Q2 are used to drive the ultraviolet LED chip 5. When the input signal is amplified, the operating states of the transistor Q1 and the transistor Q2 are adjusted according to the level change of the output signal, so as to control the brightness of the LED.
By adjusting the intensity of the input signal, the brightness of the LED can be controlled. The circuit realizes the brightness adjusting function of the LEDs by amplifying input signals and controlling current and driving single LEDs by using the transistor Q1 and the transistor Q2. According to the intensity variation of the input signal, the brightness of the LED will also vary accordingly.
The embodiment is provided with an independent detection chamber 1, can be combined with a radionuclide automatic separation device to automatically sample and feed, and can also manually sample and feed; the light source module 4 sends light with a specific wavelength band into the detection chamber 1 through the first light path, the light with the specific wavelength band can be manually adjusted according to the needs of the sample, for example, the light can be automatically adjusted through an optical component of a specific optical filter, the light signal is output through the absorption and transmission principle of the light after the sample in the detection chamber 1 receives the light with the specific wavelength, the light signal acquisition module 3 acquires the light signal of the sample through the second light path at fixed points, the position and the number of the acquisition points can be adjusted according to the measurement needs in the automatic signal detection analysis software developed in the embodiment, and the light signal acquisition module 3 transmits the acquired light signal to the upper computer 9 for data processing analysis.
When the embodiment works, a sample to be detected is added into the colorimetric test tube 2 after being subjected to color development treatment, the sample to be detected is vertically placed into the detection chamber 1 from the upper part of the detection chamber 1, the light source module 4 is controlled to emit light, the sample receives ultraviolet light transmitted in a first light path below the sample in the detection chamber 1, light absorption and transmission are carried out, the upper computer 9 controls the light signal acquisition module 3 to capture an image of a fixed point, the acquired image is returned to the upper computer 9 through the signal processing module 11, pixel information of the image is extracted, the obtained pixel information is analyzed and subjected to matrixing treatment through a written program in the upper computer 9, and R, G, B three-channel information values obtained through analysis and standard curves of respective channels are substituted and calculated, so that a detection result of the sample is finally obtained and is output to a software interface through the program.
The device of this embodiment is constructed for modularization, can be according to the demand each module of convenient replacement, the poor module of substitution operating mode or upgrade the hardware module to guarantee whole detecting system's job stabilization nature, adapt to the quick detection demand of various samples.
The device of the embodiment has small whole volume which can be controlled at 0.5dm 3 In the following, the weight can be controlled within 300g according to the selection of the module, is equivalent to two smart phones, has very strong portability, can overcome the shortcoming that current uranium detection device is difficult to move fast and arrange, and this embodiment can easily shift and carry, need not extra auxiliary device system (such as carrier gas) simultaneously, can realize the quick response and the arrangement of device.
The embodiment has good measurement range and measurement accuracy, can finish the experimental verification of the detection feasibility of 0.01mg/L-1.00mg/L of standard uranium solution concentration, can reach 0.001mg/L of detection accuracy, and can meet the rapid detection requirement of radioactive element uranium in the environment according to the maximum content of uranium in drinking water reported by World Health Organization (WHO) of 0.2 mg/L.
The detection speed of this embodiment is fast, especially for samples with low concentration level, if the radioactive technology is adopted for measurement, a longer technical time is required to reduce errors, but only sample adding and sampling operations are required after sample preparation of this embodiment, and the actual detection process is very fast (about 1 s). If an automatic device is used, the sample adding and sampling operations can be automated, and meanwhile, the detection efficiency of the device is higher.
The embodiment establishes a set of unique upgrading mechanism, and can be conveniently combined with other equipment by arranging a series of software and hardware interfaces and a modularized detection device, so that the application range of the device is expanded. In particular, the device can be combined with a radionuclide automatic separation device to realize the stay detection of samples and maximally realize the detection efficiency and portability of radioactive element uranium.
Embodiment two:
the portable rapid uranium detection system is matched with signal automatic detection analysis software (a portable rapid uranium detection method), realizes rapid matrixing processing of collected optical signals, and gives out a working curve of the system through R, G and B three-channel code conversion and independent data fitting, and automatically processes and analyzes signals of samples to be detected and outputs the signals.
Programming for the computer and operating system used is written using programming language c++ for controlling the operation of the individual components, such as the LED switches and voltages, the output and processing of data in the detection chamber 1.
The portable rapid uranium detection method comprises two parts of standard working curve comparison and actual sample measurement, wherein standard working curve drawing is carried out before sample measurement, the RGB channel value of standard solution is input and the known concentration is obtained, so that standard working curve drawing is realized, the standard working curve obtained in the detection of unknown samples is substituted into corresponding color indexes for concentration conversion, and finally the standard working curve is presented on an interface. The user can set and monitor the operation of the portable rapid detection system of uranium through the interface, and meanwhile, information such as a process, result feedback and the like is received. Generally, the user interface needs to be easy to use, simple to operate, friendly to the interface, etc., to improve the ease of use and popularity of the portable rapid detection system for uranium.
As shown in fig. 11, the portable rapid detection method of uranium provided by the present invention is applied to the portable rapid detection system of uranium in the first embodiment, and the portable rapid detection method of uranium includes:
step 1: acquiring a fluorescence signal image of a solution to be detected; the fluorescence signal of the solution to be detected is developed by adding azo arsine III into the solution to be detected, the fluorescence signal is excited by the light source module 4 to be generated, and the fluorescence signal image is acquired by the optical signal acquisition module 3.
Step 2: and extracting an R channel information value, a G channel information value and a B channel information value of the fluorescent signal image.
Step 3: according to the B channel information value, determining the uranium concentration in the solution to be detected by utilizing a B channel standard working curve; the B channel standard working curve is determined according to the concentration of the standard solution and the B channel information value of the standard solution.
Step 4: according to the R channel information value, determining a first reference value of uranium concentration in the solution to be detected by utilizing an R channel standard working curve; the R channel standard working curve is determined according to the concentration of the standard solution and the R channel information value of the standard solution.
Step 5: according to the G channel information value, determining a second reference value of uranium concentration in the solution to be detected by utilizing a G channel standard working curve; the G-channel standard operating curve is determined from the concentration of the standard solution and the G-channel information value of the standard solution.
Step 6: and carrying out error correction on the uranium concentration measured value in the solution to be detected according to the uranium concentration first reference value and the uranium concentration second reference value, and determining the uranium concentration in the solution to be detected.
In practical applications, two methods can be used for error correction: (1) linear correction: if the error is due to systematic deviation or instrument drift, a linear correction method is used. And performing linear regression on the difference between the measured result (first reference value) of the R channel standard working curve compared with the known concentration sample and the true value of the R channel standard working curve to obtain a function or formula corrected by the second reference value. Then, substituting the measurement result (uranium concentration measurement value) of the sample to be detected into the correction function to obtain a corrected concentration value (uranium concentration in the solution to be detected). (2) And (5) weight correction: the measurement errors of different samples are different in size, and a weighting correction method can be adopted. And according to the measurement error of each sample, giving different weights to the measurement results of different samples, and then carrying out weighted average or weighted fitting on the measurement results to obtain corrected concentration values (uranium concentration in the solution to be detected).
As an alternative embodiment, step 2 specifically includes:
splitting a channel of the fluorescent signal image; the channels include an R channel, a G channel, and a B channel.
And carrying out matrixing treatment on the fluorescent signal image, and extracting an R channel information value, a G channel information value and a B channel information value.
In practical application, referring to the schematic diagram of the device in fig. 1, after the sample to be detected (solution to be detected) is subjected to color development, the sample to be detected is added into a colorimetric test tube 2, the sample to be detected is vertically placed into a detection chamber 1 from the upper part, a light source module 4 is controlled to emit light, the sample to be detected receives ultraviolet light transmitted in a lower light path (a first light path) in the chamber, light absorption and transmission are performed, an upper computer 9 controls an optical signal acquisition module 3 to capture an image (fluorescent signal image) of a fixed point, pixel information of the obtained fluorescent signal image is returned to the upper computer 9, the obtained pixel information is subjected to analysis and matrixing processing in the upper computer 9, and R, G and B three-channel information values obtained by analysis are substituted into standard working curves of respective channels to calculate, so that a detection result (namely a concentration value determined by using a standard working curve of a B channel) of the sample to be detected is finally obtained and output to a software interface. The R/G channel value has important application in the aspects of error check and system check, and whether the detected concentration is reliable or not can be judged through the change of the R/G value in the concentration change process.
The system of the invention needs to perform calibration work of a standard working curve before use, by setting standard uranyl solutions with different concentration gradients (at least three groups of standard solutions are added), inputting the concentration of the standard uranyl solutions into a software program under the interface visual prompt of developed software, operating a system to perform measurement work of uranium elements, automatically performing data processing after receiving fluorescent signal images of the standard uranyl solutions, and visually outputting the working curve and the linear regression coefficient thereof.
The following are examples of the present invention for calibration of the system operating curve using standard uranyl solutions:
sample pretreatment and sample addition
Six groups of standard uranyl solutions (0, 0.01mg/L,0.05mg/L,0.10mg/L,0.50mg/L and 1.00 mg/L) with different concentrations are set in the preliminary experiment, wherein blank is used as a reference, the pH value is adjusted to be 2 by using a nitric acid solution with the concentration of 0.5mol/L, an azo arsine III solution is added for color development, and after the color development, the treated samples are respectively added into a detection system in sequence according to the operation prompt of software.
Calibration of sample rapid detection operation and system standard operation curve
The detection system respectively carries out rapid detection analysis on the added standard samples, analyzes and converts the read color block codes (six groups of color block codes are respectively #faebff, # ead f6, # d6d3fc, # bacdff, #95a5ff, # 8176ff) to obtain three groups of values of R channel, G channel and B channel, and as shown in table 1, carries out linear fitting analysis on the concentration of the standard solution by (S0-S)/S0 (S0 is the RGB channel value of the blank, S is the RGB channel value of the sample), so as to obtain the standard working curve of the series of samples. In particular, as shown in fig. 12, the set of standard operating curves is obtained as y=0.41x+0.08, r 2 =0.99995, with good use conditions.
Table 1 RGB channel value statistics for six sets of color block codes
| Concentration | Colorlump | RGB | C R | C G | C B |
| 0 | #faebff | 250，235，255 | 250 | 255 | 235 |
| 0.01 | #ead7f6 | 234，215，246 | 234 | 246 | 215 |
| 0.05 | #d6d3fc | 214，181，252 | 214 | 252 | 211 |
| 0.1 | #bacdff | 186，168，255 | 186 | 255 | 205 |
| 0.5 | #95a5ff | 149，98，255 | 149 | 255 | 165 |
| 1 | #8176ff | 129，50，255 | 129 | 255 | 118 |
| 5 | #3812cb | 56，18，203 | 56 | 203 | 18 |
(III) quick measurement of sample
When the system is used, continuous and rapid measurement can be realized only by calibrating once, the on-site measurement operation only needs sample adding and sampling, and the rest operations can be completed by the operation of the upper computer 9. If the automatic device is used in combination, complete automatic rapid detection can be realized, no additional operation is needed on site, the automatic device has rapid response and signal input and output functions, signal acquisition of a single sample can be completed only by 1s after calibration is completed, signal matrixing treatment can be rapidly and conveniently realized, interference of variegated colors (measuring containers) is eliminated, signals of three channels R, G and B are respectively subjected to comprehensive comparison, and an optimal detection result is automatically output.
The invention can rapidly complete the detection and analysis of the radioactive element uranium, has the advantages of simplicity, reliability and high efficiency, and greatly enhances the upgradeability and portability of the device due to the modularized design. The system can be combined with the radionuclide automatic separation device to realize automatic stay detection, so that the complex steps of manual operation and measurement are avoided, the labor intensity of personnel is greatly reduced, and meanwhile, the safety of analysis personnel can be greatly improved due to the minimal contact with aggressive acid and the remote operation of radioactive samples.
The principles and embodiments of the present invention have been described in this specification with reference to specific examples, the description of which is only for the purpose of aiding in understanding the method of the present invention and its core ideas; also, it is within the scope of the present invention to be modified by those of ordinary skill in the art in light of the present teachings. In view of the foregoing, this description should not be construed as limiting the invention.
Claims (6)
1. A portable rapid detection system for uranium, characterized in that: the portable rapid uranium detection system can be combined with a radionuclide automatic separation device, the radionuclide automatic separation device is used for carrying out matrix separation and enrichment of target uranium to obtain a solution to be detected, the portable rapid uranium detection system comprises an upper computer, a detection chamber, a colorimetric test tube, an optical signal acquisition module and a light source module, the colorimetric test tube is used for containing the solution to be detected and fluorescent reagents, the colorimetric test tube is a disposable plastic test tube, the colorimetric test tube is placed in the detection chamber, the light source module comprises an ultraviolet light LED chip, the light source module outputs an optical signal to irradiate on the colorimetric test tube, the fluorescent reagents in the colorimetric test tube generate fluorescent signals after excitation of the light source module, and the fluorescent signals return to the colorimetric test tube and are acquired by the optical signal acquisition module, and the optical signal acquisition module is electrically connected with the upper computer;
the upper computer is used for determining the uranium concentration in the solution to be detected according to the fluorescent signal image of the solution to be detected, which is acquired by the optical signal acquisition module.
2. The portable rapid detection system of uranium according to claim 1, wherein: the light signal acquisition module is arranged on one side of the colorimetric test tube, and the light source module is positioned above the colorimetric test tube or below the colorimetric test tube.
3. The portable rapid detection system of uranium according to claim 1, wherein: the light source module further comprises a supporting structure, a radiating fin and a fan, wherein the ultraviolet LED chip is arranged on the supporting structure, one end of the radiating fin is connected with the supporting structure, and the other end of the radiating fin is provided with the fan.
4. The portable rapid detection system of uranium according to claim 1, wherein: and an optical filter is arranged between the light source module and the colorimetric test tube.
5. The portable rapid detection system of uranium according to claim 1, wherein: the optical signal acquisition module is a camera.
6. A portable rapid uranium detection method is characterized in that: the portable rapid detection method of uranium is applied to the portable rapid detection system of uranium according to any one of claims 1 to 5, and the portable rapid detection method of uranium comprises:
acquiring a fluorescence signal image of a solution to be detected; the fluorescence signal of the solution to be detected is generated through excitation of the light source module, and the fluorescence signal image is acquired through the light signal acquisition module;
extracting an R channel information value, a G channel information value and a B channel information value of the fluorescent signal image;
according to the B channel information value, determining a uranium concentration measurement value in the solution to be detected by utilizing a B channel standard working curve; the standard working curve of the B channel is determined according to the concentration of the standard solution and the information value of the B channel of the standard solution;
according to the R channel information value, determining a first reference value of uranium concentration in the solution to be detected by utilizing an R channel standard working curve; the R channel standard working curve is determined according to the concentration of the standard solution and the R channel information value of the standard solution;
according to the G channel information value, determining a second reference value of uranium concentration in the solution to be detected by utilizing a G channel standard working curve; the standard working curve of the G channel is determined according to the concentration of the standard solution and the G channel information value of the standard solution;
and carrying out error correction on the uranium concentration measured value in the solution to be detected according to the uranium concentration first reference value and the uranium concentration second reference value, and determining the uranium concentration in the solution to be detected.
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