KR101876686B1 - Separation Method and Apparatus of radioactive pollution soil - Google Patents

Abstract

The present invention relates to a device and a method to treat radioactively polluted soil. More specifically, the present invention includes: a first radioactivity measurement device (100) measuring whether soil suspected to be polluted by radioactivity contains radioactivity or not; a wet granularity separating device (200) receiving and classifying radioactively polluted soil by granularity; a second radioactivity measurement device (300) measuring whether soil having a granularity of no less than 1 mm contains radioactivity or not; a washing device (400) washing the soil, having a granularity of no less than 1 mm and determined by a second radioactivity measurement device (300) to contain radioactivity, and soil having a granularity of no less than 75 μm to less than 1 mm; a third radioactivity measurement device (500) measuring whether the soil washed by the washing device (400) contains radioactivity or not; a dehydrating device (600) removing moisture from soil having a granularity of less than 75 μm; and a process water supply device (700) supplying process water to at least one among the granularity separating device (200) and the dehydrating device (600).

Description

TECHNICAL FIELD The present invention relates to a radioactive contaminated soil composite separation method and apparatus,

The present invention relates to an apparatus and a method for treating radioactive contaminated soil, and more particularly, to an apparatus and method for treating radioactive contaminated soil for judging contamination of soil, sorting and cleaning the soil by particle size, and then recycling the washing water.

When the atomic nucleus of an unstable element collapses on its own, it emits radiation from the inside, and its ability to collapse per unit time is called radioactivity. In addition, nuclear nuclei with these properties are called radionuclides (nuclear species), and substances containing radionuclides are called radioactive materials.

In the natural world, uranium and radium, as well as the atomic nuclei of about 40 elements with a relatively large atomic number, belong to the atomic nucleus reaction, and artificially radioactive ones are hydrogen atom 1, rutherfordium ) And about 1,000 species of radioactive nuclei.

On the other hand, such radiation is useful in the medical field to kill cancer cells and prevent cancer cells from propagating to the surroundings. However, when an excessive amount of radiation is applied to a human body, tissues or organs are seriously damaged in a short time. Acute radiation such as cerebrovascular syndrome, GI syndrome, and hematopoietic syndrome may occur depending on the exposure dose. Symptom development and progression due to radiation exposure depends on radiation dose.

Therefore, substances containing or likely to contain radioactive materials must be determined by the presence and concentration of radioactive materials, and whether the radioactive materials are to be discarded after measurement. In particular, when dismantling nuclear power plants, large amounts of soil and concrete wastes are generated, and these wastes include polluted soil, soil containing extremely low level radioactivity near the restriction release level, soil containing high level radioactivity Although the materials are distributed at various concentrations, the soil treatment methods so far depend on simple disposal.

In order to analyze the radioactivity concentration of these wastes, it is required to measure the radioactivity concentration at a very low level. Therefore, it is difficult to measure the radioactivity concentration in the laboratory after collecting the representative sample or in the field using the in-situ equipment for a long time .

On the other hand, although the radiation detector has no detectable nuclide discrimination ability, it is possible to produce a large-sized measuring instrument and a nuclide discriminating ability, but it is difficult to detect the nuclide with low detection efficiency. However, these detectors are separated and can not be used efficiently There is a problem.

Korean Patent Publication No. 2014-0042067 Japanese Laid-Open Patent Publication No. 2015-59789 Japanese Patent Publication No. 5450356

Disclosure of Invention Technical Problem [8] Accordingly, the present invention has been made keeping in mind the above problems occurring in the prior art, and an object of the present invention is to provide an apparatus and a method for treating radioactive contaminated soil that can efficiently treat radioactive contaminated soil.

Further, in the present invention, by using a measuring device provided with two kinds of detectors, it is possible to complement defects of the respective detectors and to detect contamination of wastes generated in large quantities and to quickly check the stock amount of radionuclides. And an object of the present invention is to provide a processing apparatus and method.

In order to solve the above problems, an apparatus for treating a radioactive contaminated soil according to the present invention comprises a first radioactivity measuring device 100 for measuring radioactivity by supplying soil suspected of radioactive contamination; A wet granulation separator (200) for receiving soil contaminated with radioactivity and classifying the particles by granularity; A second radioactivity measuring device 300 for measuring the presence or absence of radioactivity in a soil having a particle size of 1 mm or more; A washing device 400 for washing the soil of 1 mm or more and the soil having a particle size of 75 μm or more and less than 1 mm which is judged to contain radioactivity in the second radiation measuring device 300; A third radioactive measuring device 500 for measuring whether radioactivity is contained in the soil washed by the cleaning device 400; A dewatering device 600 for removing moisture contained in the soil having a particle size of less than 75 mu m; And a process water supply device (700) for supplying process water to at least one of the particle size separator (200) and the dewatering device (600).

The first radioactive measuring device 100, the second radioactive measuring device 300, and the third radioactive measuring device 500 for measuring whether or not radioactivity is contained in the soil may be the same one.

In addition, the particle size separating apparatus 200 may include a primary screen 210, a secondary screen 220, and a multi-cyclone 230.

The primary screen 210 separates soil having a particle size of 1 mm or more, and the multi-cyclone 230 can be separated into a soil having a particle size of 75 μm or more and less than 1 mm or less than 75 μm.

The dewatering device 600 may be a filter press.

The process water supply device 700 may further include a separation membrane 710 for separating the cesium component from the waste water generated in the particle size separation device 200 and / or the cleaning device 400, A permeate water reservoir 720 for storing the removed permeate water, an adsorption tower 730 for receiving concentrated water containing cesium by the separation membrane 710 to adsorb and remove cesium, and an effluent of the adsorption tower 730 And a detector 740 that measures the concentration of cesium in the sample.

The first radioactive measuring device 100, the second radioactive measuring device 300 and the third radioactive measuring device 500 may include a main body 110 having a predetermined size and forming a space through the inside thereof, A polyvinyltoluene (PVT) detector 120 and a NaI (TI) scintillation detector 130 provided in the bottom of the space and the ceiling.

The NaI (TI) scintillation detector may be provided in the groove 111 on the upper portion of the main body.

In addition, the method of treating radioactive contaminated soil according to the present invention is characterized in that the soil suspected to be contaminated with radioactivity is supplied to a radioactivity measuring device to classify the soil into a contaminated soil and a non-contaminated soil, A second step of supplying the soil to the particle separator 200 and sorting the soil by the particle size, the third step of supplying the soil having a particle size of 1 mm or more to the radiation measuring apparatus in the second step, A fourth step of supplying the soil having a particle size of not less than 1 mm and the soil having a particle size of not less than 75 μm and less than 1 mm to the washing apparatus 400 to wash the soil, The soil washed in step 5 is supplied to a radioactivity measuring device to classify it into a contaminated soil and a non-contaminated soil; and in the second step, the soil having a particle size of less than 75 탆 is supplied to the dehydrator 600 And a sixth step of removing water contained in the soil by rushing, wherein the fourth and sixth steps are sequentially performed or simultaneously performed.

The method may further include a seventh step of supplying the process water to the particle size separator 200 and / or the cleaning device 400 in the fourth step, in the second step, And the fourth step may be performed sequentially or simultaneously.

The seventh step includes a seventh step of collecting the waste liquid discharged from the second step and / or a fourth step, a seventh step of supplying the waste liquid to the separation membrane 710 to remove the cesium component, The seventh step in which the permeated water in which the cesium component is separated is stored in the reservoir tank 720 and the concentrated water containing cesium is supplied to the adsorption tower 730 to adsorb and remove cesium, The method may further include a seventh step of supplying cesium to the storage tank 720 when the concentration of the cesium is within a predetermined range and returning the cesium to the waste solution reservoir 750 when the concentration is outside the predetermined range.

Further, the method may further include a seventh step of replacing or regenerating the adsorbent in the adsorption tower 730 after the step 7-4.

In addition, in the first, third and fifth steps of classifying the contaminated soil into the non-contaminated soil, the step of supplying the sample to the at least one radiation measuring apparatus provided with the first detector and the second detector at a first rate Measuring the radiation of the sample with the first detector, sorting the sample into non-contaminated samples if the measured value of the first detector is less than the restriction release level, And measuring the radiation of the sample with the second detector and analyzing the nuclides and the total counting rate included in the sample with the second detector, wherein the second rate is less than the first rate Can be fast.

The regulatory release level may be 0.1 Bq / g.

If the measured value of the second detector is less than 1.0 Bq / g but less than 1.0 Bq / g, the sample is classified and discharged as a low contaminated sample while maintaining the sample feed rate at the second rate. If the measured value of the second detector is 1.0 Bq / g, the sample is classified and discharged as a high-contaminated sample while changing the supply rate of the sample to the third rate. If the measured value of the second detector is less than 0.1 Bq / g, Wherein the third velocity is slower than the first velocity and faster than the second velocity.

The first speed may be 1.5 to 2.5 cm / sec, the second speed may be 0.25 to 0.35 cm / sec, and the third speed may be 0.4 to 0.5 cm / sec.

According to the present invention, a separation membrane, an adsorption tower, and a radioactive material detector are provided, and the waste fluid generated in the contaminated soil treatment can be reused, thereby reducing the processing cost of the radioactive contaminated soil.

According to the present invention, since the feeding rate of the sample is changed according to the measured range of the radioactive concentration, the time required for analyzing the sample can be shortened.

According to the present invention, it is possible to complement defects of each detector by using a reliable PVT detector and a NaI (TI) scintillation detector capable of quantitatively analyzing both quantitative analysis and a wide temperature change, Can be improved.

1 is a conceptual diagram illustrating a process for treating a radioactive contaminated soil according to the present invention.
2 is a front view of the radiation measuring apparatus.
3 is a side view of the radiation measuring apparatus.
4 is a detailed conceptual diagram illustrating the supply of process water.
5 is a flow chart for explaining a method for measuring soil contamination using a radiation measuring apparatus.

Hereinafter, an apparatus and method for treating a radioactive contaminated soil according to the present invention will be described with reference to the accompanying drawings.

The use of the terms "comprises", "having", or "having" in this application is intended to specify the presence of stated features, integers, steps, components, parts, or combinations thereof, But do not preclude the presence or addition of features, numbers, steps, operations, components, parts, or combinations thereof.

Also, unless otherwise defined, all terms used herein, including technical or scientific terms, have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. Terms such as those defined in commonly used dictionaries are to be interpreted as having a meaning consistent with the contextual meaning of the related art and are to be interpreted as either ideal or overly formal in the sense of the present application Do not.

1 is a conceptual diagram illustrating a process for treating a radioactive contaminated soil according to the present invention. 1, the apparatus for treating a radioactive contaminated soil according to the present invention comprises a radioactive first measuring device 100, a wet particle separator 200, a second radioactive measuring device 300, a cleaning device 400, A third radioactive measurement device 500, a dehydration device 600, and a process water supply device 700.

More specifically, the first radioactivity measuring apparatus 100 is a device for classifying soil into a contaminated soil and a non-contaminated soil by receiving a soil which is likely to be contaminated with radioactive material, such as a site or a demarcation site of a nuclear power plant, The classification method and the configuration of the apparatus will be described later.

The wet particle size separator 200 is a device for sorting soil after supplying some process water to the soil determined as contaminated soil among the soil discharged from the first measurement device 100. The wet particle separator 200 may include a primary screen 210, a secondary screen 220, and a multi-cyclone 230. This is to maximize the efficiency of the cleaning and further reduce the cost of treatment of contaminated soil.

First, the primary screen 210 is classified into a soil having a particle size of 1 mm or more and a soil having a particle size of less than 1 mm, for example, a trommel screen. The primary reason for separating the soil around 1 mm in size is that it is suitable for massive separation of the soil. The secondary screen 220 and the multi-cyclone 230 are separated into soil having a particle size of less than 1 mm and smaller than 75 μm and less than 1 mm, and less than 75 μm.

The second radioactive measuring apparatus 300 measures radioactive inclusion in a soil having a particle size of 1 mm or more separated by the primary screen 210 and classifies the soil into a contaminated soil and a non-contaminated soil.

The cleaning apparatus 400 receives the process water from the process water supply device 700 and receives the process water from the process equipment 400 through the soil measurement apparatus 200, Is a device for washing soil having a diameter of 75 μm or more and less than 1 mm.

Here, the washing apparatus 400 is not particularly limited as long as it is an apparatus capable of washing the soil, but may be, for example, a washing apparatus equipped with a stirrer capable of mixing the soil with the process water.

The third radioactivity measuring apparatus 500 measures radioactive inclusion in the soil that has been washed in the washing apparatus 400, and classifies the contaminated soil and the non-contaminated soil. Although not shown in the drawing, the cleaning device 400 includes the process water, so it is preferable that the cleaning device 400 is dehydrated through a known solid-liquid separator and then supplied to the third measuring device.

On the other hand, the dehydrator 600 is a device for removing moisture by receiving soil having a particle size of less than 75 μm separated from the multi-cyclone 230, and the soil from which moisture has been removed is designated as radioactive waste. The reason why the soil of less than 75 탆 is designated as the whole waste is because the radioactive material is not easily removed due to small particle size even if it is washed, so it is advantageous in terms of treatment cost not to perform contamination confirmation or to perform additional washing. Here, the dewatering device 600 is preferably a filter press, but it is not limited thereto.

The first radioactive measurement device 100, the second radioactive measurement device 300 and the third radioactive measurement device 500 may have one or more configurations having the same configuration. In other words, when there are few soil suspected to be contaminated with radioactivity, one identical measuring apparatus can be used repeatedly. On the contrary, when there is a large number of soil and it is necessary to continuously treat the soil, three measuring apparatuses may be separately provided.

2 is a front view of the radiation measuring apparatus, and Fig. 3 is a side view of the radiation measuring apparatus. 2 and 3, a radiation measuring apparatus according to the present invention includes a main body 110, a first detector 120, a second detector 130, a conveyor belt 140, A driving unit 150, and a control unit (not shown). The main body 110 is provided with a lead shielding body and has two side surfaces facing each other so as to allow a sample S to be described later to pass therethrough. . Also, a first detector 120 is provided on the ceiling and bottom of the main body 110, and a second detector 130 is provided on the groove 111.

2 and 3 show that two first detectors 120 are provided on each of the ceiling and the bottom and one second detector is provided on the groove 111. However, It is obvious that the number of detectors may be different.

Also, as described above, the first detector 120 is preferably a polyvinyltoluene (PVT) detector, and the second detector 130 is preferably a NaI (TI) flash detector, but it is not limited thereto .

A conveyor belt 140 on which the sample S is placed passes through both side surfaces of the main body 110 and a driving roller 150 for driving the conveyor belt 140 is mounted on the conveyor belt 140, Located below. Since the configuration of supplying the sample S using the driving roller 150 and the conveyor belt 140 as described above corresponds to a known technique, a detailed description thereof will be omitted.

Subsequently, a certain amount of water (water) is required to separate the soil and wash the soil. In this process, a waste liquid containing cesium, which is a radioactive material, is generated. The process water supply device 700 of the present invention supplies the process water to the particle size separation device 200 and the cleaning device 400 and simultaneously purifies the generated waste fluid to be recycled so as to minimize the amount of waste liquid generated, Thereby reducing the processing cost. 4, the process water supply device 700 includes a separation membrane 710, a permeated water storage tank 720, an adsorption tower 730, a detector 740, and a waste liquid storage tank 750.

The waste liquid storage tank 750 functions to store the waste liquid generated from the particle size separator 200 and the cleaning device 400 and the separation membrane 710 receives the waste liquid of the waste liquid storage tank 750 Separate with concentrated water containing large amounts of water and cesium. The separation membrane 710 is preferably a nanofiltration membrane or a reverse osmosis membrane capable of removing an ion component. In order to more efficiently operate the separation membrane 710, an appropriate pretreatment such as coagulation sedimentation, ultrafiltration or microfiltration is performed It is more preferable to remove the particulate matter and then supply it to the separation membrane 710.

The adsorption tower 730 is supplied with concentrated water containing cesium and adsorbs and removes cesium. For example, the adsorption tower 730 is filled with zeolite capable of effectively adsorbing cesium. Similarly, the particulate matter may be removed by performing pretreatment, for example, coagulation sedimentation, ultrafiltration or microfiltration, so that adsorption of cesium can be effectively performed, and then supplied to the adsorption tower 730.

The detector 740 is for judging to what extent cesium is contained in the effluent of the adsorption tower 730.

Referring to Figs. 1 and 4 again, a method for treating radioactive contaminated soil will be described. The method for treating radioactive contaminated soil according to the present invention is characterized in that the soil suspected to be contaminated with radioactive material is supplied to a radiation measuring device to classify the contaminated soil and the non-contaminated soil in a first step, A second step of supplying the soil to the particle size separating apparatus 200 and classifying the soil by the particle size, the third step of supplying the soil having a particle size of 1 mm or more to the radiation measuring apparatus and classifying the soil into the contaminated soil and the non- A fourth step of supplying the soil of 1 mm or more, which is judged to contain radioactivity, and the soil having a particle size of 75 μm or more and less than 1 mm in the second step to the washing apparatus 400 to wash the soil, To a radioactivity measuring device to classify the polluted soil into a contaminated soil and a non-contaminated soil. In the second step, the soil having a particle size of less than 75 탆 is supplied to a dehydrator 600 to remove water Removing the sixth step, and comprises a seventh step of supplying process water to a particle size separation device 200 and the cleaning unit 400 for.

Here, the seventh step of supplying the process water may be performed simultaneously with the second step of separating the soil by the particle size and the fourth step of washing the soil, and it is obvious that the seventh step may be sequentially performed.

The seventh step of supplying the process water includes a seventh step of collecting the waste liquid discharged in the second and / or fourth steps, a seventh step of collecting the waste liquid discharged from the seventh step of supplying the waste liquid to the separation membrane 710, Step 7-2 is a seventh step in which the permeated water from which the cesium component has been separated is stored in the reservoir tank 720 and the concentrated water containing cesium is supplied to the adsorption tower 730 to adsorb and remove cesium. The concentration of cesium contained in the effluent is measured and supplied to the reservoir tank 720 in a predetermined range, specifically less than 0.1 Bq / g. When the concentration is less than 0.1 Bq / g, the cesium is returned to the waste liquid reservoir 750, The adsorbent of the adsorption tower 730 is replaced or regenerated in step 7-5 and the adsorbent in the adsorption tower 730 is replaced or regenerated in step 7-5.

Here, in step 7-5, the concentration of cesium detected by the detector 740 can be continuously or discontinuously measured to determine whether the adsorbent has a capability of adsorbing.

5 is a flowchart illustrating a method for measuring soil contamination using the radiation measuring apparatus of the present invention. The method for measuring soil contamination using a radioactivity measuring device can be performed in the same manner in the first stage, the third stage and the fifth stage, which are classified as contaminated soil and non-contaminated soil.

As shown in FIG. 5, the radioactive contamination measuring method includes an S-1 step of supplying a sample to a radiation measuring apparatus provided with a radiation first detector and a second detector at a first speed, S-2 step of measuring the radiation; if the measurement value of the first detector is less than the restriction release level, the sample is classified and discharged as non-contaminated sample; (S-3) for measuring the radiation of the sample with the second detector, analyzing the nuclides included in the sample and the total counting rate by the second detector, and (S-4) If the measured value of the second detector is 1.0 Bq / g or more, the supply rate of the sample is classified as the lowest contaminated sample while the supply rate of the sample is maintained at the second rate. While changing to the third speed, If the measurement value of the second detector is less than 0.1 Bq / g, the sample is classified into a non-contaminated sample while changing the sample feed rate to the first rate, and then the sample is discharged. .

More specifically, in the step S-1, the sample is supplied to the radiation measuring apparatus shown in Figs. 2 and 3, in which the radiation first detector and the second detector are provided together at a first speed, The first detector measures the radiation contained in the sample.

A sample suspected of containing or containing radioactive material shall be supplied to the radioactivity measuring device to determine whether it is contained at the level of regulated release level, more specifically 0.1 Bq / g or more. At this time, the level of the deregistration contamination level is measured using a first detector, more specifically, a PVT (polyvinyltoluene) detector. PVT (polyvinyltoluene) detector is difficult to discriminate nuclides specifically, but it is possible to measure the total amount of radionuclides contained in the sample and to complete the measurement in a relatively short time.

Therefore, in step S-1, it is quickly and quantitatively analyzed whether the sample contains a radioactive material and a certain degree of radioactive material.

On the other hand, the second detector may be a NaI (TI) scintillation detector, while the NaI (TI) scintillation detector requires a comparatively long measurement time, but it can be quantitatively analyzed with a specific nuclide contained in the sample. Therefore, the NaI (TI) scintillation detector, which is the second detector, may be used as the secondary detector while performing the presence and the total amount analysis of the radiation material using the PVT (polyvinyltoluene) detector as the primary detector. At this time, the second detector used as the secondary detector performs the background fluctuation measurement and the monitoring of the concentration ratio of the contaminated nuclides. In other words, even if it is not contaminated, related data such as nuclear concentration of radioactivity for these samples may be necessary for self-disposal.

Here, a preferable first speed for supplying the sample is 1.5 to 2.5 cm / sec, and a more preferable first speed is 2 cm / sec.

Step S-3 is a step of determining whether to change the supply speed of the sample according to the measured value. More specifically, if the measured value by the first detector is less than 0.1 Bq / g, it is determined that the sample is not contaminated with radioactivity, and the separated sample is discharged as a non-contaminated sample. The first speed is maintained. As described above, since the first detector is difficult to judge a nuclide, but can quantitatively analyze at a high speed, the first rate is maintained so that many samples can be measured in a short period of time.

On the other hand, if the measured value by the first detector is 0.1 Bq / g or more, the sample feed rate is changed to the second rate, and the sample that has passed through the measuring apparatus is discharged as a contaminated sample. Of course, if additional analysis such as specific nuclides is required, it is obvious that the sample can be re-supplied to the measuring device and measured again at the second speed.

The second speed is slower than the first speed, preferably 0.25 to 0.35 cm / sec, more preferably 0.3 cm / sec. As described above, when the sample supply rate is detected to be 0.1 Bq / g or more, changing the sample supply rate to the second rate, which is slower than the first rate, is performed by using a NaI (TI) flash detector as a second detector capable of simultaneously performing nuclide analysis and quantitative analysis This is to perform the precision analysis using.

Step S-4 is a step of accurately analyzing the radionuclides included in the sample and the total counting rate with the second detector, NaI (TI) flash detector, as described above. At this time, the NaI (TI) scintillation detector is used as a main detector, and the PVT (polyvinyltoluene) detector is used as a sub-detector. The NaI (TI) scintillation detector has the advantage of being able to quantitatively analyze with nuclides, but it is susceptible to changes in temperature and humidity, and therefore there is a possibility of fluctuation in detection efficiency. On the other hand, PVT (polyvinyltoluene) There is an advantage that there is almost no change in the detection efficiency. Therefore, the total coefficient ratio of the NaI (TI) and PVT (polyvinyltoluene) detectors according to the temperature is determined in advance and the NaI (TI) flash detector is checked for abnormality.

 For example, the total coefficient ratio at a calibration temperature of 23 ° C (standard Ratio = total counting rate of NaI scintillation detector at 23 ° C / total counting rate of PVT detector at 23 ° C) is preset to standard Ratio, (Tl) of the NaI (Tl) scintillator detector is determined by determining that the measured ratio (the total counting rate at the NaI scintillator detector temperature / the total counting rate at the PVT detector at the measuring temperature) It is determined whether or not it is normal.

0.7 * Standard Ratio <Measurement Ratio <1.3 * Standard Ratio (Relation 1)

If it is out of the range of the above-mentioned relational expression 1, various warning signals such as a warning sound may be transmitted and, if necessary, the measurement may be forcibly stopped.

If the total coefficient ratio of the NaI (TI) flash detector and the PVT detector is preliminarily determined so as to have a constant relationship with the temperature as described above, the reliability of the measured value of the NaI (TI) flash detector There is an advantage that it can be.

Step S-5 is a step of determining whether to change the supply speed of the sample according to the measured value in the step S-4.

More specifically, if the measured value by the second detector is less than 0.1 Bq / g, it is determined that the sample is not contaminated with radiation, and the sample is classified into non-contaminated samples and discharged. In addition, Is changed to the first speed.

If the measured value by the second detector is 0.1 Bq / g or more and 1.0 Bq / g or less, the sample passed through the measuring device is classified as a low-contaminated sample and discharged, and the feed rate of the sample is maintained at the second rate. If the measured value of the second detector is 1.0 Bq / g or more, the sample feed rate is changed to the third rate, and the sample passing through the measuring device is classified and discharged as a high-level contaminated sample. Here, the third speed is faster than the first speed but slower than the second speed, preferably 0.4 to 0.5 cm / sec, more preferably 0.45 cm / sec. Of course, if the measured value is more than 0.1 Bq / g but less than 1.0 Bq / g, especially between 0.1 and 0.3 Bq / g, similar to the deregulation concentration, the sample can be re- It is obvious.

On the other hand, when the measured value by the second detector is 1.0 Bq / g or more, which is 10 times the deregulation concentration, the reason why the supply rate of the sample is changed more rapidly (changing from the second rate to the third rate) It is intended to shorten the measurement time because the radioactive material is contained at a high concentration. On the other hand, when the measured value by the second detector is 0.1 Bq / g to 1.0 Bq / g, the reason why the supply rate of the sample is kept at the second lowest rate is the range similar to the deregulation concentration, .

As described above, in the present invention, since the supply rate of the sample is changed according to the measured radioactivity concentration range, it is possible to shorten the time required for analyzing the sample, and to provide a reliable PVT detector with quantitative analysis, The reliability of the measured values can be improved by using a nuclide and a quantitative NaI (TI) scintillation detector.

Having thus described a particular portion of the present invention in detail, those skilled in the art will appreciate that these specific embodiments are merely preferred embodiments and that the scope of the present invention is not limited thereby, It will be apparent to those skilled in the art that various changes and modifications can be made within the scope of the invention, and that such modifications and variations are intended to fall within the scope of the appended claims.

100: First radioactivity measuring device
110: main body 111:
120: first detector 130: second detector
140: conveyor belt 150: drive roller
200: particle size separator
210: primary screen
220: Secondary screen
230: Multicylon
300: Second radioactivity measuring device
400: Cleaning device
500: Radioactive third measuring device
600: Dewatering device
700: Process water feeder
710: Membrane
720: Permeate storage tank
730: Adsorption tower
740: Detector
750: Waste liquid storage tank
S: Sample

Claims (16)

A first radioactive measuring device 100 for measuring the presence or absence of radioactivity by supplying soil suspected of radioactive contamination;
A wet granulation separator (200) for receiving soil contaminated with radioactivity and classifying the particles by granularity;
A second radioactivity measuring device 300 for measuring the presence or absence of radioactivity in a soil having a particle size of 1 mm or more;
A washing device 400 for washing the soil of 1 mm or more and the soil having a particle size of 75 μm or more and less than 1 mm which is judged to contain radioactivity in the second radiation measuring device 300;
A third radioactive measuring device 500 for measuring whether radioactivity is contained in the soil washed by the cleaning device 400;
A dewatering device 600 for removing moisture contained in the soil having a particle size of less than 75 mu m; And
And a process water supply device (700) for supplying process water to at least one of the particle size separator (200) and the dewatering device (600).
The method according to claim 1,
Characterized in that the first radioactive measuring device (100), the second radioactive measuring device (300) and the third radioactive measuring device (500) for measuring whether or not the soil contains radioactivity are the same one .
The method according to claim 1,
Characterized in that the particle separation apparatus (200) comprises a primary screen (210), a secondary screen (220) and a multi cyclone (230).
The method of claim 3,
Wherein the primary screen (210) separates the soil having a particle size of 1 mm or more, and the multi-cyclone (230) separates the soil into a soil having a particle size of 75 μm or more and less than 1 mm or less than 75 μm .
The method according to claim 1,
Wherein the dewatering device (600) is a filter press.
The method according to claim 1,
The process water supply device 700 includes a separation membrane 710 for separating the cesium component from the waste water generated in the particle size separation device 200 and / or the cleaning device 400;
A permeated water storage tank 720 in which cesium-free permeated water is stored by the separation membrane 710;
An adsorption tower 730 through which the concentrated water containing cesium is supplied by the separation membrane 710 to adsorb and remove cesium; And
And a detector (740) for measuring the concentration of cesium contained in the effluent of the adsorption tower (730).
The method according to claim 1,
The first radioactive measuring device 100, the second radioactive measuring device 300 and the third radioactive measuring device 500 include a main body 110 having a predetermined size and passing through the inside to form a space, (PVT) detector 120 and a NaI (TI) scintillation detector 130 provided on the inner bottom and the ceiling of the apparatus for treating radioactive contaminated soil.
8. The method of claim 7,
Wherein the NaI (TI) scintillation detector is provided in a groove (111) in the upper part of the body part.
A first step of supplying the soil suspected of radioactive contamination to a radioactivity measuring device to classify the contaminated soil and the non-contaminated soil;
A second step of supplying the soil classified as the contaminated soil to the particle separator 200 and classifying the soil classified by particle size in the first step;
A third step of supplying the soil having a particle size of 1 mm or more to the radiation measuring apparatus in the second step to classify the soil into the contaminated soil and the non-contaminated soil;
A fourth step of supplying the soil of at least 1 mm determined to contain radioactivity in the third step and the soil of 75 탆 or more and less than 1 mm in particle size in the second step to the washing apparatus 400 to wash the soil;
A fifth step of supplying the soil washed in the fourth step to a radioactivity measuring device to classify the contaminated soil and the non-contaminated soil; And
And a sixth step of supplying the soil having a particle size of less than 75 mu m to the dewatering apparatus 600 to remove moisture contained in the soil in the second step,
Wherein the fourth step and the sixth step are performed sequentially or simultaneously.
10. The method of claim 9,
Further comprising a seventh step of supplying the process water to the particle size separator (200) and / or the cleaning device (400) in the second step in the second step,
Wherein the seventh step is performed sequentially or simultaneously with the second step and the fourth step.
11. The method of claim 10,
The seventh step includes a seventh step of collecting the waste liquid discharged in the second step and / or the fourth step;
(7-2) separating the cesium component by supplying a waste liquid to the separation membrane (710);
A seventh step of storing the permeated water in which the cesium component has been separated in the storage tank 720 and supplying the concentrated water containing cesium to the adsorption tower 730 to adsorb and remove cesium; And
The method further comprises a seventh step of measuring the concentration of cesium contained in the effluent of the adsorption column 730 and supplying the cesium to the reservoir tank 720 if the concentration is within a predetermined range, Lt; RTI ID = 0.0 &gt; of &lt; / RTI &gt; the radioactive contaminated soil.
12. The method of claim 11,
Further comprising a seventh step of replacing or regenerating the adsorbent of the adsorption tower (730) after the step (7-4).
10. The method of claim 9,
In a first step, a third step and a fifth step of classifying the contaminated soil and the non-contaminated soil, supplying the sample to the at least one radiation measuring device provided with the first detector and the second detector at a first speed;
Measuring radiation of the sample with the first detector;
Separating the sample into non-contaminated samples if the measured value of the first detector is less than the regulatory release level, and changing the supply rate of the sample to a second rate if the measured value is greater than the regulatory release level; And
Measuring the radiation of the sample with the second detector and analyzing the nuclide and the total counting rate contained in the sample with the second detector,
Wherein the first rate is faster than the second rate.
14. The method of claim 13,
And the regulatory release level is 0.1 Bq / g.
15. The method of claim 14,
If the measured value of the second detector is less than 1.0 Bq / g, the sample is classified and discharged as a low contaminated sample while maintaining the sample feed rate at the second rate. If the measured value of the second detector is 1.0 Bq / g, the sample is classified and discharged as a high-level contaminated sample while changing the supply rate of the sample to the third rate. If the measured value of the second detector is less than 0.1 Bq / g, the supply rate of the sample is changed to the first rate, And classifying and discharging it as a sample,
Wherein the third rate is slower than the first rate and is faster than the second rate.
16. The method of claim 15,
Wherein the first rate is 1.5 to 2.5 cm / sec, the second rate is 0.25 to 0.35 cm / sec, and the third rate is 0.4 to 0.5 cm / sec.

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