KR101964099B1 - A radiation detecting devece for detecting a radionuclide in a water pipe, a water purifier including the same, and a method for detecting a radionuclide using the same - Google Patents

Abstract

According to the present invention, provided is a radiation detecting device in a water pipe comprising a solution supply pipe, a shielding material, and a radiation detector which is wound on a water pipe in the shielding material, wherein the water pipe is bypassed from the solution supply pipe, and detects the radioactive nuclide in the solution continuously flowing in the water pipe through the radiation detector in real-time. According to the present invention, the use of the radiation detecting device enables detection of radioactive nuclides included in the water, specifically in flowing water, in real-time for water harmful to the human body not to be consumed. The detecting device is inexpensive and is highly utilized as the device can be easily installed in a general household water purifier.

Description

FIELD OF THE INVENTION [0001] The present invention relates to a radiation detecting apparatus, a water purifier including the radiation detecting apparatus, and a radiation detecting method using the radiation detecting apparatus. }

The present invention relates to a radiation detection device in a water pipe, a water purifier including the radiation detection device in the water pipe, and a radiation detection method in a water pipe using the radiation detection device in the water pipe.

Radiation measurements that measure radiation from an object are widely used in a variety of fields such as nuclear power facilities and medical facilities, as well as cargo entering and exiting airports and ports. As an example, Korean Patent No. 1581004 ("Exit Vehicle Radiation Monitoring System ", hereinafter referred to as prior art 1) discloses a technique for checking the presence or absence of radiation of a vehicle installed in a doorway and passing through the doorway. The system disclosed in the prior art document 1 includes a plastic scintillator for generating scintillation light when a light of a specific wavelength is received, thereby analyzing a scintillation signal generated in the scintillation object by radiation emitted from the object to measure the presence or absence of radiation.

A more detailed description of the scintillator is as follows. An inorganic scintillator, such as NaI (TL), can generate photons of a specific intensity proportional to the energy of the incident radiation to measure the energy of the incident radiation. Therefore, inorganic scintillators are mainly used for nuclide analysis based on energy and intensity of incident radiation. On the other hand, the organic scintillator such as PVT (Polyvinyltoluene) has a low density and it is difficult to measure the energy of the incident radiation because the probability of occurrence of interaction with the incident radiation due to the photoelectric effect is low. Therefore, the organic scintillator only measures the intensity of the incident radiation . However, plastic organic scintillators are widely used for measuring the presence or absence of radiation in cargo, because they are easier to manufacture than inorganic scintillators and can be manufactured in sizes larger than m ² . In the radiation measurement system of the above-mentioned prior art document 1, as described in the use of a plastic scintillator, that is, an organic scintillator, a cargo radiation detection system generally installed at an airport or a port entrance is a PVT plastic having a volume of 25 L to 65 L A scintillator is used.

However, in such a radiation detection system, not only the presence of radiation but also the presence or absence of artificial radiation, that is, the function of determining the nuclide of artificial radiation, is also required. As described above, if a radiation detector using an inorganic scintillator is used, the presence or absence of artificial radiation can be easily determined because the radiation energy and intensity can be measured and analyzed for nuclides. However, when a radiation detector using an organic scintillator is used, Since we mainly measure only the intensity of artificial radiation, we should distinguish between artificial radiation and natural radiation.

To date, natural radiation and artificial radiation have been classified into two categories: first, direct comparison of energy spectral data measured with plastic scintillation data to background spectral data; second, determination of weighted energy values of energy spectra measured with plastic scintillators; . The first method, that is, a method of directly comparing spectral data is disclosed in Korean Patent Laid-Open Publication No. 2016-0060208 ("Method and apparatus for separating radionuclides using plastic scintillators", hereinafter referred to as Prior Art 2) The method is disclosed in detail in Korean Patent Publication No. 2010-0033175 ("Plastic scintillation-based radiation detector and method for detecting radionuclides using the same, hereinafter referred to as Prior Art 3).

However, considering the vehicle speed (up to 18 km / h) and the length (up to 15 m) of the vehicle passing through the actual cargo radiation detection system, the vehicle passing time is within 3 seconds for short time and within 10 seconds for long time, The above two methods may be difficult to be practically used. Also, if there are several sources of radiation, it can be an environment that is more difficult to judge.

On the other hand, it is a common fact that alpha and beta particles and gamma rays emitted from radioactive materials are harmful to the human body. Recently, interest in health has increased, and attention has been paid to the relatively small amount of radioactivity that can be exposed in daily life It is developing.

However, while the boundaries and attention to radiation hazards increase, the radioactivity can not be visually confirmed, so separate equipment is required to confirm this.

As a result, measuring instruments that can measure the radioactivity of food and various items when they are carried by people and carry them are in widespread use. However, they have not been used yet. This means that every time they come into contact with various goods and foods, This is also caused by the hassle of measuring.

Water, on the other hand, needs to be consumed more than a certain amount every day, so it should pay attention to the radioactivity levels of the daily intake of water, but most people do not care much about the radioactivity levels of the daily intake of water. In other words, people usually drink purified water through a water purifier in the home or workplace, but do not pay much attention to the radiation level of the water discharged through the water purifier, and only think of drinking purified water through a water purifier It is common.

In this regard, U.S. Patent No. 9,689,995 discloses the detection of radon contained in water.

It is an object of the present invention to provide a radiation detecting apparatus in a water pipe, a water purifier including the radiation detecting apparatus in the water pipe, and a radiation detecting method in a water pipe using the radiation detecting apparatus in the water pipe.

In order to achieve the above object,

According to a first aspect of the present invention,

A solution supply pipe;

A shield; And

A radiation detector wound around the water pipe in the shield;

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The water pipe is bypassed from the solution supply pipe,

And detecting the radionuclides in the solution continuously flowing through the water pipe through the radiation detector in real time,

A radiation detection device in a water pipe is provided.

In addition, the second aspect of the present invention,

There is provided a water purifier including the water detection device in the water pipe according to the first aspect of the present invention.

The third aspect of the present invention,

The solution was continuously supplied through a solution supply pipe,

A part of the supplied solution is supplied to the water pipe bypassed to the solution supply pipe,

The solution supplied to the water pipe continuously flows along the water pipe wound around the radiation detector,

Wherein the radionuclide in the solution flowing along the water pipe is detected in real time using the radiation detector,

A method for detecting radiation in a water pipe is provided.

The use of the radiation detection apparatus according to the present invention can detect radionuclides contained in the water flowing in the water pipe in real time so that it does not consume water harmful to the human body. It is advantageous in that it can be installed easily.

1 is a schematic view showing a radiation detection apparatus in a water pipe according to the present invention,
FIG. 2 is a graph showing energy spectral data of various sources measured by a radiation detector using a plastic scintillator according to an embodiment of the present invention. FIG.
FIG. 3 is a graph showing a count ratio according to energy values of various sources according to the first method of the present invention,
4 is a graph for explaining a method of calculating a row count sum and a high count sum using specific energy spectrum data according to a second method of the present invention,
FIG. 5 is a graph showing a count ratio according to energy values for various sources according to a second method of the present invention,
6 is a graph showing a standardized count ratio according to energy values for various sources according to a third method of the present invention,
7 is a graph showing cumulative count values according to energy values for various sources according to a fourth method of the present invention,
FIG. 8 is a graph showing a first standardized cumulative count value according to energy values for various sources according to a fifth method of the present invention.

According to a first aspect of the present invention,

A solution supply pipe 110;

A shielding body 140; And

A radiation detector 130 wound around the water pipe 120 in the shield 140;

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The water pipe 120 is bypassed from the solution supply pipe 110,

And detecting in real time the radionuclides in the solution flowing continuously through the water pipe (120) through the radiation detector (130)

And provides a radiation detection apparatus 101 in the water pipe.

Hereinafter, the radiation detecting apparatus 101 in the water pipe according to the first aspect of the present invention will be described in detail with reference to FIG.

First, in the present invention, the reason for detecting the radionuclide is defined as follows in order to distinguish between natural radiation and artificial radiation. It is well known that radiation below a certain level does not cause a significant adverse effect on the human body, and that such a degree of fine radiation is generally emitted to objects in the natural world. Such radiation is called natural radiation. On the other hand, artificial radioactive materials such as cesium (Cs-137) and cobalt (Co-60) emit more radioactive rays than natural radiation, and if this amount of radiation is increased, the human body may be adversely affected. In other words, radiation emitted from such artificial radioactive materials is called artificial radiation. Therefore, the radiation detection apparatus of the present invention may be performed to detect artificial radiation harmful to the human body.

In addition, in comparison with the natural radiation measured in a state in which nothing is detected as a radionuclide (which is generally referred to as a "background state"), radiation which can be presumed to be radiation generated in a specific radioactive material, . Therefore, in order to detect radionuclides, it is the most fundamental step to obtain energy spectrum data using a radiation detector.

On the other hand, the radiation detection apparatus in the water pipe of the present invention introduces existing algorithms or new discrimination equations and algorithms, without introducing new apparatuses or parts, but using existing radiation detectors and detection systems as they are. From this viewpoint, in the present invention, the method of obtaining the energy spectrum data by the radiation detector itself or the radiation detector is the same as the conventional method, so that the description thereof will be briefly described.

A method of obtaining energy spectrum data from a radiation detector will be briefly described as follows. For example, when the radiation detector is a radiation detector using a plastic scintillator, if a plastic scintillator is irradiated with radiation from an object, a scintillation signal is generated in the plastic scintillation material. It transforms the flash signal into an electrical signal, amplifies its size, and removes noise to convert it into an analytical signal. The converted signal appears as a pulse, which is counted and stored according to the magnitude of the voltage value. Each process in which the pulses of the respective voltage values are counted and cumulatively managed in the allocated buffer for a predetermined time is referred to as energy. Through this process, the energy spectrum data represented by the count value according to the energy value can be obtained. As described above, the radiation detector using the plastic scintillator finds the energy spectrum data in this manner (the energy spectrum graph obtained by this method is disclosed in all of the above-mentioned prior art documents 1 to 3), and further detailed explanation is omitted do.

This energy spectral data depends on the nuclide of the material that is the source (source) that generates the radiation. Therefore, ideally, if you know in advance what type of energy spectral data is coming from a nuclide in advance, you will be able to determine the nuclide of the source contained in the object from the measured energy spectral data.

The radiation detection apparatus 101 may include a solution supply pipe 110. The solution may be introduced into the radiation detecting apparatus 101 through the solution supplying pipe 110, but the present invention is not limited thereto.

In addition, the solution may include various solutions such as water (H ₂ O) or wastewater, but is not limited thereto.

For example, the solution supply pipe 110 may be a stainless steel pipe, a steel pipe, a stainless steel corrugated pipe, a copper pipe, a polyvinyl chloride (PVC) pipe or the like, It is not.

Meanwhile, the radiation detecting apparatus 101 may include a shielding body 140. The shield 140 may be formed outside the radiation detector 130 and the radiation may not be radiated to the radiation detector 130 by the shield 140. Therefore, the radiation detector 130 can easily detect only the radioactive nuclear species in the solution flowing in the water pipe 120 by the shield 140. In addition, the shield 140 may be installed only outside the radiation detector 130, and is not limited in shape or size.

The shield 140 is selected from the group consisting of lead (Pb), iron (Fe), nickel (Ni), copper (Cu), platinum (Pt), silver (Ag), gold But are not limited thereto.

The radiation detecting apparatus 101 may include a radiation detector 130 wound around the water pipe 120 in the shielding body 140. The reason why the water pipe 120 is designed to be wound around the radiation detector 130 is to increase the length of the water solution in the water pipe 120 so that the radiation detector 130 is supplied with sufficient time But is not limited to, detection of radionuclides.

The radiation detector 130 may be a detector using a gas ionizing action, a detector using a solid ionization action (semiconductor detector), or a detector using an excitation action, and preferably a detector using an excitation action.

The detector using the gas ionizing action may be, but is not limited to, an ionizer, a proportional counter, a quenching gas, or a Geiger Muller counter.

The solid ionization detector (semiconductor detector) may be, but is not limited to, a P-N junction detector, a surface barrier detector, a Li drift type (p-i-n type detector) or a high purity semiconductor detector.

In addition, the detector using the excitation function emits light of a proper wavelength when a certain atomic substance in the scintillator is irradiated, and when the atom or molecule of the substance returns to a base-excited state, Lusite) pipe, the Sb-Sc is changed from the front surface of the deposited light to the electron and amplified by a dynode to obtain an electric signal. The scintillator is an inorganic crystal type, an organic crystal type, a liquid type , Or plastic, but is not limited thereto.

Meanwhile, the flow rate of the solution in the water pipe 120 may be about 0.1 m / s to about 10 m / s, but is not limited thereto. If the flow velocity of the solution is less than 0.1 m / s, the velocity of the solution may be too small to use the radiation detection apparatus 101 in the water pipe. If the flow rate of the solution exceeds 10 m / s, ) Is too short to detect the radionuclide contained in the solution, so that the radionuclide may not be detected correctly.

The inner diameter of the water pipe 120 may be about 3 mm to about 250 mm, but is not limited thereto, and is preferably about 25 mm to about 50 mm. When the inner diameter of the water pipe 120 is less than 3 mm, the solution may not flow smoothly. When the inner diameter of the water pipe 120 is more than 250 mm, the flow rate of the solution flowing through the water pipe 120 increases, The paper may not be detected accurately.

The length of the water pipe 120 may be about 0.1 m to about 1 m, but is not limited thereto. The longer the length of the water pipe 120, the longer the time for the radiation detector 130 to detect the radionuclide contained in the solution, so that it can more accurately detect the radionuclide. Therefore, as the number of times the water pipe 120 winds the radiation detector 130, the radioactive nuclear species contained in the solution can be more accurately detected.

In addition, the radiation detecting apparatus 101 may detect the radionuclides in the solution continuously flowing through the water pipe 120 through the radiation detector 130 in real time.

The radiation detecting apparatus 101 may further include a display unit 150 so that the user can view the radionuclide in the solution in real time. However, the present invention is not limited thereto.

The radiation detecting apparatus 101 may be supplied with a solution through the solution supply pipe 110 and a part of the solution may flow to the water pipe 120 bypassed to the solution supply pipe 110. The solution flowing through the bypassed water pipe 120 may be detected by passing through the outside of the radiation detector 130 to detect radioactive nuclides included in the solution, and then connected to the solution supply pipe 110. [ Further, since the solution flowing through the radiation detecting apparatus 101 flows continuously, the solution in which the radioactive nuclide is detected can be continuously used.

The second aspect of the present invention provides a water purifier including the water detection device 101 in the water pipe according to the first aspect of the present invention. Although the detailed description of the parts overlapping with the first aspect of the present application is omitted, the description of the first aspect of the present invention can be applied equally to the second aspect.

The solution flowing into the radiation detecting apparatus 101 according to the first aspect of the present invention may be water, and the lower part of the solution supplying pipe 110 may be connected to the water purifier. Accordingly, the user may consume the water by continuously supplying the water detected with the radioactive nuclide through the radiation detecting device 101 to the water purifier. That is, it may be possible to safely consume water because it is possible to include radioactive material in the water before ingesting water.

The third aspect of the present application

The solution is continuously supplied through the solution supply pipe 110,

A part of the supplied solution is supplied to the water pipe 120 bypassed to the solution supply pipe 110,

The solution supplied to the water pipe 120 continuously flows along the water pipe 120 wound around the radiation detector 140,

And detecting the radionuclide in the solution flowing along the water pipe 120 in real time using the radiation detector 140. [

A method for detecting radiation in a water pipe is provided.

Although the detailed description of the parts overlapping with the first aspect and the second aspect of the present application is omitted, the description of the first aspect and the second aspect of the present invention may be applied equally to the third aspect, .

First, the method for detecting radiation in the water pipe includes continuously supplying the solution through the solution supply pipe 110. [

The solution may include, but is not limited to, various solutions such as water (H ₂ O) or wastewater.

For example, the solution supply pipe 110 may be a stainless steel pipe, a steel pipe, a stainless steel corrugated pipe, a copper pipe, a polyvinyl chloride (PVC) pipe or the like, It is not.

Next, a method of detecting radiation in the water pipe includes supplying a portion of the supplied solution to the water pipe 120 bypassed to the solution supply pipe 110.

At this time, the inner diameter of the water pipe 120 may be about 3 mm to about 250 mm, but is not limited thereto, and is preferably about 25 mm to about 50 mm. When the inner diameter of the water pipe 120 is less than 3 mm, the solution may not flow smoothly. When the inner diameter of the water pipe 120 is more than 250 mm, the flow rate of the solution flowing through the water pipe 120 increases, The paper may not be detected accurately.

The length of the water pipe 120 may be about 0.1 m to about 1 m, but is not limited thereto. The longer the length of the water pipe 120, the longer the time for the radiation detector 130 to detect the radionuclide contained in the solution, so that it can more accurately detect the radionuclide. Therefore, as the number of times the water pipe 120 winds the radiation detector 130, the radioactive nuclear species contained in the solution can be more accurately detected.

Next, a method of detecting radiation in the water pipe includes a step in which the solution supplied to the water pipe 120 continuously flows along the water pipe 120 wound around the radiation detector 140.

At this time, the radiation detector 130 may be a detector using a gas ionization action, a detector using a solid ionization action (semiconductor detector), or a detector using an excitation action, and preferably a detector using an excitation action.

The detector using the gas ionizing action may be, but is not limited to, an ionizer, a proportional counter, a quenching gas, or a Geiger Muller counter.

The solid ionization detector (semiconductor detector) may be, but is not limited to, a P-N junction detector, a surface barrier detector, a Li drift type (p-i-n type detector) or a high purity semiconductor detector.

In addition, the detector using the excitation function emits light of a proper wavelength when a certain atomic substance in the scintillator is irradiated, and when the atom or molecule of the substance returns to a base-excited state, Lusite) pipe, the Sb-Sc is changed from the front surface of the deposited light to the electron and amplified by a dynode to obtain an electric signal. The scintillator is an inorganic crystal type, an organic crystal type, a liquid type , Or plastic, but is not limited thereto.

Meanwhile, the flow rate of the solution in the water pipe 120 may be about 0.1 m / s to about 10 m / s, but is not limited thereto. If the flow velocity of the solution is less than 0.1 m / s, the velocity of the solution may be too small to use the radiation detection apparatus 101 in the water pipe. If the flow rate of the solution exceeds 10 m / s, ) Is too short to detect the radionuclide contained in the solution, so that the radionuclide may not be detected correctly.

Next, a method of detecting radiation in the water pipe includes detecting in real time the radionuclide in the solution flowing along the water pipe 120 using the radiation detector 140. [

At this time, in order to more accurately detect the radionuclide in the flowing solution, the radiation detecting apparatus 101 may include the shielding body 140. The shield 140 may be formed outside the radiation detector 130 and the radiation may not be radiated to the radiation detector 130 by the shield 140. Therefore, the radiation detector 130 can easily detect only the radioactive nuclear species in the solution flowing in the water pipe 120 by the shield 140. In addition, the shield 140 may be installed only outside the radiation detector 130, and is not limited in shape or size.

The shield 140 is selected from the group consisting of lead (Pb), iron (Fe), nickel (Ni), copper (Cu), platinum (Pt), silver (Ag), gold But are not limited thereto.

On the other hand, the radiation detecting apparatus 101 in the water pipe according to the present invention and the method for detecting radiation in the water pipe using the apparatus (method for detecting radionuclides) do not introduce new apparatuses or parts but use existing radiation detectors and detection systems , And introduces an existing algorithm or a new discriminant equation and algorithm.

Hereinafter, the new discrimination equations and algorithms will be described in detail.

In the first method,

A method for detecting a radionuclide using energy spectrum data represented by a count according to an energy obtained from a radiation detector,

The background energy spectrum data measured without the object to detect the radionuclide and the object energy spectrum data measured in the presence of the object are used to divide the object energy spectrum data into arbitrary energy values into the background energy spectrum data and calculate the count ratio Calculating;

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A method for detecting radionuclides is provided.

The method of detecting the radionuclide includes the steps of: measuring background energy spectrum data measured without an object to detect a radionuclide and object energy spectrum data measured in the presence of the object to obtain object energy spectrum data for an arbitrary energy value; And the background energy spectrum data to calculate the count ratio.

At this time, the count ratio is defined as a value obtained by dividing the object energy spectrum data by background energy spectrum data with respect to an arbitrary energy value, and the count ratio of the background energy spectrum data becomes 1 regardless of the energy value.

3 is a graph showing a count ratio according to energy values for various sources. Referring to the graph, it can be seen that peaks of each radionuclide have different peaks. Compared with FIG. 2, it can be seen that each radionuclide is more easily distinguished.

The method for detecting the radionuclide may further include discriminating the radionuclide detected from the object by comparing the count ratio with a previously prepared radionuclide count ratio.

At this time, the comparison may be to find and compare a minimum energy value within a certain range of the count ratio. The predetermined range may be about 1.1 times to about 1.2 times as much as one reference, but is not limited thereto. Preferably, the step of finding an energy value having the count ratio equal to 1 may be included. That is, referring to FIG. 2, the count ratio of the background energy spectrum data is 1 regardless of the energy value, and the count ratio of all the radionuclides converges to 1 as the energy increases. At this time, since the minimum energy value at which the count ratio converges to 1 differs depending on the type of radionuclide, the radionuclide may be detected by finding a minimum energy value within a certain range of the count ratio.

Further, in a specific radionuclide, the minimum energy value within a certain range from 1 and the minimum energy value within a certain range of the specific radionuclide prepared in advance may not always appear to be the same value. And the minimum energy value within a certain range, it is judged to be the same radionuclide if the error is within about 20%.

Meanwhile, the energy value of the radionuclide species prepared in advance means the value of energy stored in the radionuclide according to the first aspect of the present invention.

On the other hand, the comparison may be to find and compare an energy value having the maximum count value. That is, referring to FIG. 3, it can be seen that the energy representing the maximum count ratio is different for each type of radionuclide, and therefore, the energy value having the maximum count value is found and compared with the previously prepared radionuclide type count ratio May be to detect radionuclides. At this time, in the specific radionuclide, the energy value representing the maximum count ratio and the energy value representing the maximum count ratio of the specific radionuclide prepared in advance may not appear to be the same value, and the energy representing the maximum count ratio of the prepared radionuclide And if it is within an error range of about 20%, it is judged to be the same radionuclide.

Also, the comparison may be to compare the pattern of the count ratio with energy. That is, referring to FIG. 3, the patterns of the count ratios according to energies are different for each kind of radionuclide, and it may be possible to detect radionuclides by searching for the same pattern by comparing with the pattern of the count ratio of the prepared radionuclide species .

Also, the step of performing the count ratio calculation may be performed while changing the energy value, and the count ratio may be defined within a predetermined arbitrary energy period, i.e., a predetermined lower energy value to an upper energy value have.

At this time, the lower limit energy value may be generally determined as 0 or 1. [ The energy value corresponds to an index as a discrete value. At this time, in general, when the index numbering is started from 0 or starting from 1 is widely used, if the index numbering starts from 0, the lower limit energy value can be 0, and if the index numbering is 1 The lower limit energy value may be 1.

Also, the upper limit energy value may be determined as the highest one of the actual energy values, but not limited thereto, and may be determined as an appropriate energy value.

That is, referring to FIG. 3, after calculating the count ratio using the background energy spectrum data and the object energy spectrum data, if the count ratio of the energy is represented in one graph, the count ratio value for each radionuclide It is easy to distinguish them. Therefore, it may be possible to detect the radionuclide by comparing the count ratio according to the energy with a previously prepared radionuclide species count ratio. As described above, the comparison is performed by finding and comparing a minimum energy value having a count ratio within a range of 1, searching for and comparing an energy value having a maximum count value, or comparing the pattern of the count ratio with energy Or may be to use them in combination.

In the second method,

A method for detecting a radionuclide using energy spectrum data represented by a count according to an energy obtained from a radiation detector,

Performing count ratio calculation for an arbitrary energy value using background energy spectrum data measured without an object to detect a radionuclide and object energy spectrum data measured in the presence of an object; And

Comparing the background count ratio and the object count ratio;

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The count ratio may be,

A ratio of a row count sum of count values below the arbitrary energy value to an arbitrary energy value divided by a high count sum of count values exceeding the arbitrary energy value or a count value less than the arbitrary energy value And a high count sum of the counts of the energy values,

A method for detecting radionuclides is provided.

In the method for detecting the radionuclide, first, step 1 is performed by using background energy spectrum data measured without an object to detect radionuclides and object energy spectrum data measured in the presence of an object, And counting ratio calculation (S100).

In this case, the count ratio may be a ratio of a row count sum of count values below the arbitrary energy value to an arbitrary energy value divided by a high count sum of the count values exceeding the arbitrary energy value, And a low count sum of count values less than the energy value divided by a high count sum of the count values of the arbitrary energy value or more.

4 is a diagram for explaining a method of obtaining a row count sum and a high count sum according to the present invention using specific energy spectrum data. The energy spectrum data shown in FIG. 4 can be applied to any energy spectral data such as background energy spectrum data or spectra of other sources, as described below.

In Fig. 4, an arbitrary energy value is indicated by an arrow point. Energy of less than or less than the arbitrary energy value is referred to as low energy, and energy above or above the arbitrary energy value is referred to as high energy around the arbitrary energy value. In the present invention, first, a high energy sum is obtained by summing the count values in the low-energy sum and the counts in the high energy.

As described above, the row count sum and the high count sum can be obtained on the basis of an arbitrary energy value, and the ratio of the row count sum divided by the high count sum is defined as the count ratio.

For example, referring to FIG. 4A, an arbitrary energy value is approximately 320 keV, and the count values for each energy value in the low energy region, which is less than or equal to the energy, are summed to yield a row count sum. Also, the high count sum is calculated by summing the count values for each energy value in the high energy region which is the arbitrary energy value, that is, energy higher than or equal to 320 keV. Then, the calculated row count sum is divided by the high count sum to calculate the count ratio. In the same manner, in FIG. 4B, an arbitrary energy value becomes about 680 keV, and the count ratio is calculated in the same manner as described above.

Next, Step 2 is a step (S200) of comparing the background count ratio and the object count ratio.

The comparing step may include comparing the background count ratio and the object count ratio to find an energy value having the same count ratio.

Further, the method may further include discriminating the radionuclide detected in the object by comparing the energy value found in the comparing step with the energy value prepared in advance.

At this time, the same energy value found in the comparing step and the prepared radioactive nuclear species energy value may not always appear as the same value, and the same energy value found in the comparing step is compared with the prepared radioactive nuclear energy value If it is within about 20% of the error range, it is judged to be the same radioactive nuclear species.

On the other hand, the previously prepared radionuclide species energy value means the energy value stored in the radionuclide according to the above method.

In the third method,

A method for detecting a radionuclide using energy spectrum data represented by a count according to an energy obtained from a radiation detector,

Performing count ratio calculation for an arbitrary energy value using background energy spectrum data measured without an object to detect a radionuclide and object energy spectrum data measured in the presence of an object;

Calculating an object normalization count ratio represented by a normalized value according to energy from an object count ratio, wherein the normalized value is defined as a ratio of an object count ratio and a background count ratio at an arbitrary energy value; And

Searching for an energy value for which the standardized value is 1 in the object standardized count ratio;

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The count ratio may be,

A ratio of a row count sum of count values below the arbitrary energy value to an arbitrary energy value divided by a high count sum of count values exceeding the arbitrary energy value or a count value less than the arbitrary energy value And a high count sum of the counts of the energy values,

A method for detecting radionuclides is provided.

That is, in the same manner as the second method, the third method also uses the background energy spectrum data measured without an object to detect the radionuclide and the object energy spectrum data measured in the presence of the object, And performing non-computation, respectively.

However, the third method differs from the second method in that it includes a step of calculating the standardized count ratio and a step of finding an energy value of which the standardized value is 1.

Hereinafter, the third method will be described in detail with respect to a configuration different from the second method.

First, as in the second method, after counting ratio calculation for an arbitrary energy value is performed, an object standardized count ratio, which is expressed as a normalized value according to energy from the object count ratio, is calculated.

At this time, the normalized value is defined as a ratio of the object count ratio and the background count ratio value to an arbitrary energy value. Hereinafter, a value obtained by dividing the object count ratio by the background count ratio is referred to as a first normalized value, and a value obtained by dividing the background count ratio by the object count ratio value is referred to as a second normalized value.

In this case, the value 1 of the step of finding the energy value may be calculated by subtracting the energy value of the object from the background first normalized or second normalized energy ratio data obtained from the background energy ratio data instead of the object energy ratio data of the first normalized or second normalized energy ratio data calculating step , And means 1 as a first normalized value or a second normalized value that is obtained at a constant value according to energy.

Further, in the method for detecting the radionuclides of the second method and the third method, the step of performing the count ratio calculation may be performed while changing the energy value, and the count ratio may be a predetermined arbitrary energy That is, within a predetermined lower limit energy value to an upper limit energy value.

At this time, the lower limit energy value may be generally determined as 0 or 1. [ The energy value corresponds to an index as a discrete value. At this time, in general, when the index numbering is started from 0 or starting from 1 is widely used, if the index numbering starts from 0, the lower limit energy value can be 0, and if the index numbering is 1 The lower limit energy value may be 1.

Also, the upper limit energy value may be determined as the highest value among the actual energy values as well. However, as shown in FIG. 2, when the energy value is in the range of 1 to 400, the count value is relatively large, that is, about 100 to 10,000. On the other hand, when the energy value is larger, . That is, referring to FIG. 2, when the energy value is greater than or equal to about 1,000, the count value is only 1 to 10, which does not have a large effect on the calculation of the row count sum value or the high count sum value as described above. In consideration of this point, the upper limit energy value can be appropriately determined to be an energy value at a point where the count value falls to or near 10 in general. In the example of the present invention, as shown in FIG. 2, since the total energy value ranges from 1 to 2,400, the upper limit energy value can be determined to be about 1,000. On the other hand, there are various cases such as when the total energy value ranges from 1 to 512, for example, from 1 to 1,024. In this case, the upper energy value may be appropriately determined as 256/512 or the like.

To summarize again, the reason for determining the upper energy value is to reduce the computational load by eliminating energies with small values that do not significantly affect the final result even when the sum of the high counts is actually calculated. Accordingly, the upper limit energy value may be appropriately determined as an energy value at a point near the point where the count value falls below 10, taking the above-mentioned matters into consideration.

In this case, the count ratio is obtained for each energy value while changing the arbitrary energy value from the lower energy value to the upper energy value. 4A shows a case where an arbitrary energy value is 320, and when a predetermined arbitrary energy interval is 1 to 800, a row count sum = (count value when the energy value is 1 + energy value) The count value when the energy value is 321, the count value when the energy value is 321, and the count value when the energy value is 322), and the high count sum = (the count value when the energy value is 321 + The count value when the energy value is 800), and from this, the count ratio value = (row count sum / high count sum) when the energy value is 320 can be obtained. 3B shows a case where the energy value is 680. Similarly, the row count sum = count value when the energy value is 1 + count value + when the energy value is 2 + count value when the energy value is 680 (The count value when the energy value is 681 + the count value when the energy value is 682 + ... + count value when the energy value is 800), and the energy value becomes And the count ratio = (low-count sum / high-count sum) at 680 is obtained. In this way, when the lower limit energy value is 1 and the upper limit energy value is 800, the count ratio value when the energy value is 1 is obtained, the count ratio value when the energy value is 2, , And the count ratio value when the energy value is 800 can be obtained.

5A and 5B, counting ratio calculation is performed using background energy spectrum data and object energy spectrum data, and a background count ratio and an object count ratio for energy are shown on one graph, It can be seen that the count ratio of the nuclides is easy to distinguish visually. In addition, since the count ratio and the backward count ratio for each radionuclide intersect once at a specific energy value, the type of the radionuclide contained in the object can be confirmed by finding an intersecting energy value.

For example, referring to FIG. 5A, it can be seen that the count ratio of Ba-133 once crosses the background count ratio and the energy value of about 100, and referring to FIG. 5b, the count ratio of Co- The intersection of the ground count ratio and the energy value of about 720 can be seen. Thus, since the count ratio of the energy of a specific radiation source intersects the background count ratio once on the graph, the energy value of the intersecting point can be read to determine the nuclide of the specific radiation source.

6A and 6B, FIG. 6A is a graph of a first normalized count ratio, which is represented by a first normalized value according to energy, FIG. 6B is a graph of a second normalized count ratio . ≪ / RTI > In a small energy interval, the first normalization count ratio has a first normalization value less than 1, but the second normalization count ratio has a second normalization value higher than 1. However, it can be seen that as the graph moves to the high energy region, the standardized value is higher than 1 and the standardized value is higher or lower, respectively.

That is, the method for detecting a radionuclide according to the third method includes detecting a radionuclide by finding an energy value at which the normalized value is 1 because the standardized count ratio of the object includes a point at which the normalized value becomes 1 have.

Specifically, in the method described in the second method, the energy value found at the step of finding the energy value at which the normalization value is 1 is compared with the energy value of the radionuclide species at which the previously prepared normalized value is 1, The radionuclide energy value at which the previously prepared standardized value becomes 1 means the energy value stored and performed according to the third method in terms of the type of radionuclide.

At this time, the energy value at which the normalized value is 1 may not always be the same value as the prepared radionuclide species energy value, and the energy value at which the standardized value is 1 is compared with the prepared radionuclide type energy value. If it is within 20% of the error range, it is judged to be the same radionuclide species.

Fourth,

A method for detecting a radionuclide using energy spectrum data represented by a count according to an energy obtained from a radiation detector,

Performing cumulative count value computation for an arbitrary energy value using the measured background energy spectrum data and the measured object energy spectrum data in the presence of the object without the object to detect radiation; And

Comparing the background cumulative count value and the object cumulative count value;

Lt; / RTI >

Wherein the cumulative count value is calculated by:

Lt; / RTI > is defined as the sum of all energy values above or above the energy value based on any energy value,

A method for detecting radionuclides is provided.

In the method for detecting the radionuclide, first, step 1 is performed by using background energy spectrum data measured without an object to be irradiated and accumulation of an arbitrary energy value using measured object energy spectrum data in the presence of the object And counting the count value, respectively (SlOO).

In this case, the cumulative count value may be defined as a sum of energy values that are greater than or equal to an energy value based on an arbitrary energy value.

The cumulative count value may be calculated by the following equation.

Where i is an arbitrary energy value, n is a last energy value, C (i) is a count value for each energy value, and S (i) is a cumulative count value for any energy value.

For example, as shown in FIG. 7, when the energy is in the range of 1 to 2,000, if the arbitrary energy is 1, the cumulative count value S (i) thereof is the sum of the count values of energy 1 to energy 2,000 . In the same manner, when the arbitrary energy is 2, the cumulative count value S (i) is a sum of the count values of energy 2 to energy 2,000.

Next, step 2 is a step (S200) of comparing the background cumulative count value and the object cumulative count value.

The comparing step may be to find a minimum energy value in which the difference between the cumulative count value of the object and the background cumulative count value is within a certain range, and the predetermined range may be about 1.1 to 1.2 times the background cumulative count value But is not limited thereto. And comparing the background accumulation count value with the object accumulation count value to find an energy value having the same cumulative count value.

The method may further include comparing the energy value found in the comparing step with a previously prepared radionuclide species energy value to distinguish the radionuclides detected in the object.

At this time, the energy value of the radionuclide species prepared in advance corresponds to the stored energy value of the radionuclide according to the fourth method.

In the fifth method,

A method for detecting a radionuclide using energy spectrum data represented by a count according to an energy obtained from a radiation detector,

Performing cumulative count value calculation for an arbitrary energy value using background energy spectrum data measured without an object to detect the radionuclide and object energy spectrum data measured in the presence of an object;

Calculating an object normalized cumulative count value represented by a normalized value according to energy from an object cumulative count value, wherein the normalized value is a normalized cumulative count value defined as a ratio of an object cumulative count value and a background cumulative count value at an arbitrary energy value Calculating step; And

Finding a minimum energy value of the object normalized accumulation count value having a normalized value within a certain range from 1;

Lt; / RTI >

Wherein the cumulative count value is calculated by:

Lt; / RTI > is defined as the sum of all energy values above or above the energy value based on any energy value,

A method for detecting radionuclides is provided.

That is, the fifth method is the same as the fourth method, and the background energy spectrum data measured without an object to detect a radionuclide and the accumulated energy spectrum data measured with the object are used to accumulate And performing count value calculation, respectively.

However, the fifth method differs from the fourth method in that it includes a step of calculating a cumulative count value of the standardized cumulative value and a step of finding an energy value having a normalized value of 1.

Hereinafter, the fifth method will be described in detail with respect to a configuration different from the fourth method.

First, after the cumulative count value calculation for an arbitrary energy value is performed as in the fourth method, an object standardized accumulation count value, which is expressed as a normalized value according to energy, is calculated from the object cumulative count value.

At this time, the normalized value is defined as a ratio of the object accumulation count value and the background accumulation count value at an arbitrary energy value. Hereinafter, a value obtained by dividing the cumulative count value of the object by the background cumulative count value is referred to as a first normalized value, and a value obtained by dividing the background cumulative count value by the cumulative object count value is referred to as a second normalized value.

A method of obtaining the first normalized value may be expressed as follows.

S i (i) is a background accumulation count value for an arbitrary energy value, Sr 1 (i) is an accumulation count value of an arbitrary energy value, Sb Is the ratio of the background cumulative count value to the cumulative count value of the object.

A method of obtaining the second standardized value may be expressed as follows.

S i (i) is a background accumulation count value for an arbitrary energy value, Sr 2 (i) is an accumulation count value of an arbitrary energy value, Sb Is the rate at which the cumulative count value of the object is divided by the background cumulative count value.

In this case, the value 1 in the step of finding the energy value may be a value obtained by subtracting the background cumulative count value from the background cumulative count value obtained from the first cumulative cumulative count value in the first normalized cumulative cumulative count value calculating step , And means 1 as a first normalized value or a second normalized value that is obtained at a constant value according to energy.

In the method of detecting the radionuclides of the fourth method and the fifth method, the step of calculating the cumulative count value may be performed while changing the energy value, and the cumulative count value may be a predetermined random value That is, within the predetermined lower limit energy value to the upper energy value.

At this time, the lower limit energy value may be generally determined as 0 or 1. [ The energy value corresponds to an index as a discrete value. At this time, in general, when the index numbering is started from 0 or starting from 1 is widely used, if the index numbering starts from 0, the lower limit energy value can be 0, and if the index numbering is 1 The lower limit energy value may be 1.

Also, the upper limit energy value may be determined as the highest value among the actual energy values, but is not limited thereto.

7, after calculating the cumulative count value using the background energy spectrum data and the object energy spectrum data, if the background cumulative count value and the object cumulative count value for the energy are shown on one graph, It can be seen that the cumulative count value for the nuclide is easy to distinguish visually. In addition, since the difference between the cumulative count value and the backlogged cumulative count value for each radionuclide is close to the specific energy value, the type of the radionuclide contained in the object can be determined by finding the minimum energy value within the predetermined range have.

For example, referring to FIG. 7, it can be seen that the count ratio of Ba-133 crosses once with the background count ratio and the energy value of about 310 keV. Thus, since the count ratio of the energy of a specific radiation source intersects the background count ratio once on the graph, the energy value of the intersecting point can be read to determine the nuclide of the specific radiation source.

Referring to FIG. 8, FIG. 8 is a graph of a first normalized cumulative count value, which is expressed as a first normalized value according to energy. The first normalized cumulative count value may have a first normalized value higher than 1, but the second normalized cumulative count value may be expected to have a second normalized value higher than 1. [ However, it can be seen that the standardized value gradually approaches 1 as the energy is moved to the high energy region in the graph.

That is, the method of detecting the radionuclide according to the fifth method may be to detect the radionuclide by finding the minimum energy value within a certain range from the standardized value of 1 because the cumulative count value of the object standardized is close to 1.

At this time, the range may be about 0.5% (1.005) to about 1% (1.01) of the background energy, but is not limited thereto.

The energy value found in the step of finding the minimum energy value within the range of 1 and the standardized value is compared with the minimum value of the radionuclide type energy having a predetermined range of 1 and a predetermined standard value, And a step of distinguishing between the two.

At this time, the minimum value of the radionuclide species energy having the standardized value prepared in advance within the range of 1 and the predetermined range means the previously stored energy value according to the fifth method.

101: Radiation detection device in water pipe
110: solution supply pipe
120: Water pipe
130: Radiation detector
140: Shielding
150:

Claims (9)

A solution supply pipe;
A shield; And
A radiation detector wound around the water pipe in the shield;
Lt; / RTI >
The water pipe is bypassed from the solution supply pipe,
And detecting the radionuclides in the solution continuously flowing through the water pipe through the radiation detector in real time,
A radiation detection apparatus in a water pipe,
The radiation detector may measure object energy spectrum data for an arbitrary energy value using background energy spectrum data measured without an object to detect radionuclides and object energy spectrum data measured in the presence of an object as background energy spectrum data The count ratio is calculated,
Wherein the counting ratio is compared with a previously prepared radionuclide counting ratio to discriminate the radionuclide detected in the object by finding and comparing the minimum energy value within a certain range with the counting ratio of 1.
The method according to claim 1,
The shield comprises a material selected from the group consisting of lead (Pb), iron (Fe), nickel (Ni), copper (Cu), platinum (Pt), silver (Ag), gold Wherein the radiation detector is disposed in the water pipe.
The method according to claim 1,
Wherein the flow rate of the solution in the water pipe is 0.1 m / s to 10 m / s.
The method according to claim 1,
Wherein the inner diameter of the water pipe is 3 mm to 250 mm.
The method according to claim 1,
Wherein the water pipe has a length of 0.1 m to 1 m.
The method according to claim 1,
Wherein the radiation detection apparatus further comprises a display unit for allowing a user to view the radionuclide in the solution in real time.
A water purifier comprising the water detection device of claim 1.
8. The method of claim 7,
Wherein the solution supply pipe of the radiation detection device in the water pipe is connected to the water purifier.
The solution was continuously supplied through a solution supply pipe,
A part of the supplied solution is supplied to the water pipe bypassed to the solution supply pipe,
The solution supplied to the water pipe continuously flows along the water pipe wound around the radiation detector,
Wherein the radionuclide in the solution flowing along the water pipe is detected in real time using the radiation detector,
A method for detecting radiation in a water pipe,
The radiation detector may measure object energy spectrum data for an arbitrary energy value using background energy spectrum data measured without an object to detect radionuclides and object energy spectrum data measured in the presence of an object as background energy spectrum data The count ratio is calculated,
Detecting the radiation in the water pipe by comparing the count ratio with a previously prepared radionuclide species count ratio to identify the radionuclide detected in the object by finding and comparing the minimum energy value within a certain range of the count ratio Way.

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