JP2006208192A - Artificial radioactivity measuring device and measuring method - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide an artificial radioactivity measuring device and a measuring method with high accuracy of measurement by measuring directly radiation from artificial radioactivity. <P>SOLUTION: In the artificial radioactivity measuring device including ultra thin flat plate type plastic scintillator detectors 12 and 22 on the both sides of a concrete 10, flat plate type NaI (Tl) scintillator detectors 13 and 23, and a pair of radiation detectors 11 and 21 consisting of aluminum cut plates 14 and 24, the simultaneous counting rate is determined, which is measured at a simultaneous counting section 31 counting the signals measured during the same time at the pair of radiation detectors 11 and 21, and then an amount of artificial radioactivity is derived, based on the simultaneous counting rate. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

  The present invention relates to an artificial radioactivity measuring device that measures the concentration of artificial radioactivity in contaminated concrete with extremely low radioactivity generated during the dismantling of nuclear reactor buildings and radioactive material handling facilities associated with decommissioning of power generation reactors. And a measuring method.

  Concrete contains natural radioactivity such as potassium 40 (K-40), uranium (U), thorium (Th) and their daughter nuclides. On the other hand, concrete that may be contaminated during the operation of the facility may be contaminated by artificial radionuclides such as cobalt 60 (Co-60) and cesium 137 (Cs-137). The level is extremely low.

  When measuring the concentration of artificial radionuclides from concrete that contains such natural radioactivity and is contaminated by artificial radioactivity, it is clear that typical test specimens that are apparently not containing artificial radioactivity in advance. Measure the measurement results, and count rates from radiation from natural radioactivity in the concrete to be measured and from environmental radiation from cosmic rays and natural radioactivity in building structural materials (supplementary explanation: there are two types of BG It is necessary to use them separately.) The so-called background is generally subtracted from the counting rate at the time of measurement of the sample and converted to an artificial radioactivity concentration.

  However, in general, the concentration of natural radioactivity varies depending on the type of specimen. Therefore, it is necessary to change the background due to natural radioactivity in this specimen depending on the type of measurement sample, that is, the type of concrete sample, the material, the type of aggregate, etc. Variations in active density can cause large errors.

  As what solves such a problem, there exists a thing described in the following patent document 1, for example. This "Method for Measuring Radioactive Concentrations of Artificial Radionuclides in Concrete" described in Patent Document 1 combines a small detector for measuring γ-ray energy with a large detector for measuring the total count rate for γ-rays. Calculate and evaluate the count rate due to the natural radioactivity of the large detector from the measured concentration of the artificial radioactivity of the detector, and calculate the net count rate due to the artificial radioactivity by subtracting it and convert it to radioactivity It is. It is said that almost uniform radioactivity concentration in the concrete of the artificial radionuclide distributed almost uniformly can be measured.

JP-A-5-333155

  In Patent Document 1 described above, from the total count rate of the large detector for measuring the total count rate for γ rays, the count rate due to natural radioactivity and the count rate of the environmental background due to cosmic rays and building structural materials are calculated. By subtracting, the gross count rate due to artificial radioactivity is calculated. In this case, in order to obtain the counting rate by natural radioactivity, the natural radioactivity concentration in concrete is obtained in advance, or the natural radioactivity concentration is calculated by adding a spectrum detector and the gross count by natural radioactivity is calculated. It is necessary to find the rate. In addition, it was necessary to set how cobalt 60 was distributed in the concrete. In order to evaluate the counting rate due to natural radioactivity in the concrete to be measured, it is necessary to correct the difference in counting rate due to the shape of the concrete and the radiation attenuation effect in the concrete. By including an error, subtracting the counting rate due to natural radioactivity and the environmental background from the measured gross counting rate to calculate the counting rate due to the artificial radionuclide is a measurement method with a large measurement error. In addition, in order to convert the counting rate by artificial radioactivity to the amount of artificial radioactivity, it is necessary to make assumptions about the distribution of artificial radioactivity. There is a problem that the error becomes particularly large when the amount of artificial radioactivity in the concrete is small.

  This invention solves the subject mentioned above, and it aims at providing the artificial radioactivity measuring apparatus and measuring method with a sufficient measurement precision by directly measuring the radiation from artificial radioactivity.

  In order to achieve the above object, an artificial radioactivity measurement apparatus according to claim 1 of the present invention is an artificial radioactivity measurement apparatus for measuring artificial radioactivity in a measurement object containing natural radioactivity. It is measured at the same time by a pair of radiation detection means arranged on both sides with the detection surface facing the measurement object and counting the counting rate due to γ rays emitted from the measurement object, and the pair of radiation detection means. A coincidence rate measuring means for measuring the measured signal, a coincidence count rate measured by the coincidence count rate measuring means and a count rate measured by the pair of radiation measuring means from the environmental background count rate and the measurement object An artificial radioactivity calculating means for obtaining the artificial radioactivity amount based on the natural radioactivity concentration is provided.

In the artificial radioactivity measurement apparatus according to the invention of claim 2, the artificial radioactivity calculation means includes count rates Ca and Cb by artificial radioactivity calculated from two count rates counted by the respective radiation detection means, Based on the coincidence counting rate C simultaneously counted by each radiation detection means, the following formula Q = Ca · Cb / 2C
The artificial radioactivity amount Q is obtained by the following.

  In the artificial radioactivity measurement apparatus according to the invention of claim 3, the radiation detection means is arranged with the detection surface facing the measurement object, and is capable of capturing β rays emitted from the measurement object and the measurement. Γ-rays emitted from the object can be transmitted, the natural radioactivity count rate by β-rays, the natural radioactivity count rate by γ-rays, and the artificial radioactivity count rate by γ-rays, A first radiation detector that counts the total counting rate, and a detection surface that is substantially the same size and shape as the detection surface of the first radiation detector, the detection surface of the first radiation detector being The γ-rays, which are arranged so as to be positioned on the non-detection surface side, are capable of capturing γ-rays emitted from the measurement object and transmitted through the first radiation detector, and counting of the natural radioactivity by γ-rays And the total counting rate which is the counting rate of the artificial radioactivity with γ rays A second radiation detector that counts and a blocking surface that is substantially the same size and shape as the detection surface of the first radiation detector, and is located on the detection surface side of the first radiation detector and the measurement And a radiation blocker arranged to overlap the target with the blocking surface facing and blocking the β-rays of the natural radioactivity emitted from the measurement target.

  In the artificial radioactivity measurement apparatus according to the invention of claim 4, the artificial radioactivity calculation means obtains a β-ray count rate in consideration of the contribution of γ rays in the count rate counted by the first radiation detector. Then, the counting rate by γ rays of the natural radioactivity is obtained from the counting rate by β rays according to the detection efficiency, and the counting rate by the γ rays of the natural radioactivity is calculated from the counting rate counted by the second radiation detector. By subtracting, the counting rate of the artificial radioactivity by γ rays is obtained.

  In the artificial radioactivity measurement apparatus according to the invention of claim 5, the radiation detection means is arranged with a detection surface facing the measurement object, can capture γ-rays emitted from the measurement object, and the natural radiation. A radiation detector that counts the total counting rate of the gamma ray counting rate and the gamma ray counting rate of the artificial radioactivity, wherein the artificial radioactivity calculation means is counted by the radiation detector It is characterized in that the counting rate by the gamma ray of the artificial radioactivity is obtained by subtracting the counting rate by the gamma ray of the natural radioactivity set by the prior analysis from the counting rate.

  In the artificial radioactivity measurement apparatus according to the invention of claim 6, the artificial radioactivity calculation means estimates the incidence rate of γ rays entering the radiation detection means from the measurement object from the shape of the measurement object, and the γ The detection efficiency of the radiation detection means is obtained based on the incidence ratio of rays and the detection ratio of γ rays incident on the radiation detection means, and the coincidence counting rate and the detection counted simultaneously by the respective radiation detection means The artificial radioactivity amount is obtained based on efficiency.

  In the artificial radioactivity measurement apparatus according to the invention of claim 7, the artificial radioactivity calculation means obtains a count rate obtained by subtracting the count rate due to the environmental background from the two count rates counted by the respective radiation detection means. The artificial radioactivity amount is obtained based on a count rate excluding environmental background components, a natural radioactivity concentration contained in the concrete, and a coincidence count rate simultaneously counted by the respective radiation detection means.

  In the artificial radioactivity measurement device according to the invention of claim 8, the artificial radioactivity calculation means obtains a count rate obtained by subtracting a count rate due to an environmental background from the two count rates counted by the respective radiation detection means, The artificial radioactivity is obtained based on the count rate excluding the environmental background component, all the radioactivity contained in the concrete, and the coincidence count simultaneously counted by the respective radiation detection means.

  The method for measuring artificial radioactivity according to the invention of claim 9 is characterized in that a counting rate by γ rays emitted from the measurement object is counted by a pair of radiation detection means arranged on both sides of the measurement object, and the pair of radiation detection means The γ-dose of the artificial radioactivity is obtained based on the coincidence counting rate measured at the same time by the radiation detection means.

  According to the artificial radioactivity measuring apparatus of the first aspect of the present invention, a pair of radiation detection means for counting the counting rate by the γ rays emitted from the measurement object is arranged on both sides of the measurement object, and a pair of radiation detection A simultaneous counting rate measuring means for counting signals simultaneously measured by the means, and the artificial radioactivity calculating means measures the simultaneous counting rate measured by the simultaneous counting rate measuring means and the counting rate measured by the pair of radiation measuring means Therefore, since the amount of artificial radioactivity is obtained based on the counting rate by the environmental background and the natural radioactivity concentration in the measurement object, it is possible to reduce the error of the artificial radioactivity and simplify the measurement work.

  According to the artificial radioactivity measurement apparatus of the invention of claim 2, the artificial radioactivity calculation means includes the count rates Ca and Cb by the artificial radioactivity calculated from the two coincidence counts counted by the respective radiation detection means, Based on the coincidence rate C counted simultaneously by each radiation detection means, the γ-dose Q of the artificial radioactivity is obtained by the formula “Q = Ca · Cb / 2C”, so the distribution of the artificial radioactivity in the concrete is assumed. It is not necessary and can measure with little error.

  According to the artificial radioactivity measuring apparatus of the invention of claim 3, the radiation detection means is configured to count the natural radioactivity β-count, the natural radioactivity γ-ray count, and the artificial radioactivity γ-ray count. The first radiation detector that counts the count rate that is the sum of the rates, the count rate by the gamma rays of the natural radioactivity that has passed through the first radiation detector, and the count rate by the gamma rays of the artificial radioactivity are summed Because it is composed of the second radiation detector that counts the counted rate and the radiation blocker that blocks the beta rays of natural radioactivity emitted from the measurement object, the natural radioactivity concentration in the concrete is obtained in advance. The measurement work can be simplified.

  According to the artificial radioactivity measuring apparatus of the invention of claim 4, the artificial radioactivity calculating means obtains the counting rate by β rays in consideration of the contribution of γ rays in the counting rate counted by the first radiation detector. Calculating the natural radioactivity γ-ray count rate according to the detection efficiency from the β-ray count rate, and subtracting the natural radioactivity γ-ray count rate from the count rate counted by the second radiation detector Therefore, since the counting rate of artificial radioactivity by γ rays is obtained, it is not necessary to obtain the natural radioactivity concentration in the concrete in advance, and the measurement work can be simplified.

  According to the artificial radioactivity measuring apparatus of the invention of claim 5, the radiation detection means counts the total count rate of the natural radioactivity count rate by γ rays and the artificial radioactivity count rate by γ rays. Since the artificial radioactivity calculation means subtracts the natural radioactivity counting rate set by prior analysis from the counting rate counted by the radiation detector, the artificial radioactivity calculation means obtains the counting rate based on the gamma rays of artificial radioactivity. Therefore, it is not necessary to assume the distribution of artificial radioactivity in the concrete, and it is possible to measure with little error.

  According to the artificial radioactivity measurement device of the invention of claim 6, the artificial radioactivity calculation means estimates the incidence rate of γ rays entering the radiation detection means from the measurement object from the shape of the measurement object, and The detection efficiency of the radiation detection means is obtained based on the incidence ratio and the detection ratio of the γ rays incident on the radiation detection means, and the artificial radiation is calculated based on the coincidence counting rate and the detection efficiency counted simultaneously by each radiation detection means. Since the capacity is obtained, it is not necessary to obtain the natural radioactivity concentration in the concrete in advance, and the measurement work can be simplified.

  According to the artificial radioactivity measurement device of the invention of claim 7, the artificial radioactivity calculation means obtains a count rate obtained by subtracting the count rate due to the environmental background from the two count rates counted by each radiation detection means, and this The gamma dose of artificial radioactivity is calculated based on the count rate excluding environmental background components, the natural radioactivity concentration contained in concrete, and the simultaneous count rate simultaneously counted by each radiation detection means. There is no need to evaluate the counting rate due to natural radioactivity from the natural radioactivity concentration in the concrete, and it is possible to reduce the error of artificial radioactivity and simplify the measurement work.

  According to the artificial radioactivity measurement apparatus of the invention of claim 8, the artificial radioactivity calculation means obtains a count rate obtained by subtracting the count rate due to the environmental background from the two count rates counted by each radiation detection means, and this The gamma dose of artificial radioactivity is calculated based on the count rate excluding environmental background components, the total radioactivity contained in the concrete, and the simultaneous count rate simultaneously counted by each radiation detection means. It is not necessary to evaluate the natural radioactivity count from the natural radioactivity concentration in the concrete, and it is possible to reduce the error of the artificial radioactivity and simplify the measurement work.

  Moreover, according to the artificial radioactivity measurement method of the invention of claim 9, the counting rate by the γ rays emitted from the measurement object is counted by the pair of radiation detection means arranged on both sides of the measurement object, Since the amount of artificial radioactivity is obtained based on the coincidence count rate measured at the same time by the radiation detection means, the amount of error is reduced because the amount of artificial radioactivity is evaluated using the gamma ray count rate of artificial radioactivity. Can be measured.

  Exemplary embodiments of an artificial radioactivity measurement apparatus and a measurement method according to the present invention will be described below in detail with reference to the accompanying drawings. Note that the present invention is not limited to the embodiments.

  FIG. 1 is a schematic diagram of an artificial radioactivity measuring apparatus according to Embodiment 1 of the present invention, and FIG. 2 is a schematic diagram showing a method for measuring radiation emitted from concrete by the artificial radioactivity measuring apparatus of Embodiment 1. 3 is an explanatory diagram for explaining the decay of cobalt 60, and FIG. 4 is a schematic diagram showing a waveform of a measurement signal input to the artificial radioactivity measurement apparatus according to the first embodiment.

  The artificial radioactivity measuring apparatus of Example 1 measures the artificial radioactivity in concrete 10 as a measuring object containing natural radioactivity as shown in FIG. That is, the artificial radioactivity measuring apparatus of the present embodiment is arranged with a detection surface facing the concrete 10 on both sides of the concrete 10, and a pair of radiation detecting apparatuses 11 for counting the counting rate by γ rays emitted from the concrete 10. , 21, a simultaneous measurement unit (simultaneous counting rate measuring means) 31 that counts only signals counted simultaneously by the pair of radiation detection devices 11, 21, and a simultaneous measurement count measured by the simultaneous measurement unit 31 And an artificial radioactivity calculation unit (artificial radioactivity calculation means) 32 for obtaining the radioactivity of the artificial radioactivity based on the two count rates counted by the rate and the pair of radiation detection devices 11 and 21.

  The radiation detectors 11 and 21 include ultrathin flat plastic scintillator detectors 12 and 22 as first radiation detectors and flat NaI (Tl) scintillator detectors 13 and 23 as second radiation detectors. And aluminum cut plates 14 and 24 as radiation blockers and counting rate calculation units 15 and 25. Here, natural radioactivity includes potassium 40 (K-40), uranium (U), thorium (Th) and its daughter nuclide. Since most of the natural radioactivity is K-40, the natural radioactivity is represented below by K-40. Artificial radioactivity includes cobalt 60 (Co-60) and cesium 137 (Cs). Artificial radioactivity is represented by Co-60.

  As shown in FIGS. 1 and 2, the ultrathin flat plate type plastic scintillator detectors 12 and 22 are arranged so that their detection surfaces face each other toward the concrete 10, and β rays emitted from the concrete 10 are detected. It can be captured and can transmit gamma rays emitted from the concrete 10. The ultra-thin flat plate plastic scintillator detectors 12 and 22 include natural radioactivity (potassium 40) β-counting rates AP and BP, natural radioactivity counting rates Kpa and Kpb, and artificial radiation. It is possible to count the count rates Apa and APb, which are the sum of the count rates Cpa and Cpb due to gamma rays of Noh (cobalt 60) and the count rates GBpa and GBpb due to environmental background components. In this case, the thickness of the ultrathin flat plastic scintillator detectors 12 and 22 is about 0.1 to 0.3 mm.

  The flat plate type NaI (Tl) scintillator detectors 13 and 23 have a detection surface having almost the same size and shape as the detection surfaces of the ultrathin flat plate type plastic scintillator detectors 12 and 22, and this detection surface is an ultrathin flat plate type plastic scintillator. The γ-rays which are arranged so as to be positioned on the non-detection surface side of the detectors 12 and 13 and are emitted from the concrete 10 and transmitted through the ultrathin flat plastic scintillator detectors 12 and 22 can be captured. Then, the counting rates Aa and Ab are counted by summing up the counting rates Ka and Kb due to γ rays of natural radioactivity, the counting rates Ca and Cb due to γ rays of artificial radiation, and the counting rates GBa and GBb due to environmental background components. can do. In this case, the thickness of the flat plate NaI (Tl) scintillator detectors 13 and 23 is about 1 cm.

  The cut plates 14 and 24 made of aluminum have a blocking surface having almost the same shape and shape as the detection surfaces of the ultrathin flat plate type plastic scintillator detectors 12 and 22, and the detection surfaces of the ultrathin flat plate type plastic scintillator detectors 12 and 13. It is located on the side so as to overlap the concrete 10 with the blocking surface facing, and the β-rays of artificial radioactivity released from the concrete 10 can be blocked. That is, the maximum energy of β rays in potassium 40 which is natural radioactivity is 1.314 MeV, the maximum energy of β rays in cobalt 60 as artificial radioactivity is 0.318 MeV, and the β energy of maximum energy is 0.318 MeV. The range in aluminum is about 1.9 mm for potassium 40 and about 0.3 mm for cobalt 60. Therefore, the beta rays (maximum energy = 0.318 MeV) in cobalt 60 can be cut off by setting the thickness of the aluminum cut plates 14 and 24 to 0.3 mm or more.

  Therefore, the radiation emitted from the concrete 10 toward the radiation detection devices 11 and 21 first reaches the cut-off surface of the aluminum cut plates 14 and 24. Here, only the β rays of artificial radioactivity are cut. Natural radioactivity beta rays, natural radioactivity and artificial radioactivity gamma rays are transmitted. Next, the remaining radiation emitted from the concrete 10 reaches the detection surfaces of the ultrathin flat plastic scintillator detectors 12 and 22, and among these, each of the natural and artificial radioactivity gamma rays is transmitted. Therefore, most of the light passes through the ultrathin flat plastic scintillator detectors 12 and 22 and reaches the detection surface of the flat NaI (Tl) scintillator detector 2. On the other hand, natural radioactive β-rays that have reached the ultrathin flat plastic scintillator detectors 12 and 22 are transmitted through the ultrathin flat plastic scintillator detectors 12 and 22 because energy is lost here and the transmission power is lost. Thus, the thick NaI (Tl) scintillator detectors 13 and 23 cannot be reached.

  The ultrathin flat plate type plastic scintillator detectors 12 and 22 and the flat plate type NaI (Tl) scintillator detectors 13 and 23 have a large area flat plate detection so that the ratio of radiation from the concrete incident on the detector increases. In order to take out the fluorescence emitted by the detector as a signal, a fluorescent fiber is set on the opposite side of the detector 12, 22, 13, 23 from the side on which the radiation is incident. It is preferable to collect and propagate the generated fluorescent light and extract it as a signal.

  The extracted optical signal is converted into an electrical signal by a photomultiplier tube (not shown), and the converted electrical signal is output to the count rate calculation units 15 and 25. In the count rate calculation units 15 and 25, the count rates APa and APb detected by the ultrathin flat plastic scintillator detectors 12 and 22 and the count rate Aa detected by the flat NaI (Tl) scintillator detectors 13 and 23 are detected. , Ab and the artificial radioactivity, that is, the counting rates Ca and Cb of the cobalt 60 by γ rays are calculated, and the simultaneous counting unit 31 calculates the simultaneous counting rate C.

Here, a method of calculating the counting rates Ca and Cb by the cobalt 60 γ rays by the counting rate calculators 15 and 25 will be described. The counting rates APa and APb by the thin plastic scintillator detectors 12 and 22 are the counting rates AP and BP by β of natural radioactivity, the counting rates Kpa and Kpb by gamma rays of natural radioactivity, and artificial radioactivity (cobalt 60). ) Of γ rays and the count rates GBpa and GBpb of environmental background components are totaled and can be expressed by the following mathematical formula.
APa = AP + Kpa + Cpa + GBpa
APb = BP + Kpb + Cpb + GBpb

The counting rates Aa and Ab by the thick NaI (Tl) scintillator detectors 13 and 23 are the counting rates Ka and Kb by γ rays of natural radioactivity, the counting rates Ca and Cb by γ rays of artificial radiation, and the environment. This is the sum of the counting rates GBa and GBb based on the background components, and can be expressed by the following mathematical formula.
Aa = Ka + Ca + GBa
Ab = Kb + Cb + GBb
Here, since what is to be obtained is the counting rates Ca and Cb by natural radiation (cobalt 60) γ rays, the above formula is modified.
Ca = Aa-Ka-GBa
Cb = Ab-Kb-GBb

In this case, since the concrete 10 has a flat plate shape, the concentration of natural radioactivity is set based on the detection efficiency from the counting rates AP and BP of the natural radioactivity β, and the shape measurement data (height and area) of the concrete 10 is set. ), The counting rates Ka and Kb of natural radioactivity with γ rays can be obtained. In addition, since the ratios Ma and Mb between the counting rate by the γ rays of the thin plastic scintillator detectors 12 and 13 and the counting rate by the γ rays of the thick NaI (Tl) scintillator detectors 13 and 23 are constant, It holds. Ma and Mb are values depending on the detector, and can be evaluated in advance.
Cpa / Ca = Kpa / Ka = Ma-GBa
Cpb / Cb = Kpb / Kb = Mb-GBb
Therefore, the counting rates AP and BP by β of natural radioactivity are obtained by the following mathematical formula.
AP = APa−Aa · Ma
BP = APb−Ab · Mb

  Further, the counting rates GBa and GBb by the environmental background component are the counting rate when the concrete is not installed in the measuring instrument or the counting rate by correcting the attenuation effect by the concrete of the γ ray of the environmental background component if necessary. It is a value that can be evaluated by taking into account the shape and density of concrete with respect to the counting rate measured in advance or obtained in advance.

By the way, the counting rates Ca and Cb of γ-rays of cobalt 60 are the artificial radioactivity entering the radiation detection devices 11 and 21 from the concrete 10 to the number of γ-rays generated from the gamma dose Q of the artificial radioactivity in the concrete 10. Γ-ray incidence ratios ωa and ωb and the artificial radiation γ-ray detection ratios εa and εb incident on the γ-ray detectors 13 and 23 of the radiation detection apparatus can be obtained by multiplying them.
Ca = Q · ωa · εa
Cb = Q · ωb · εb
In addition, the incident ratios ωa and ωb of γ rays include the effects of attenuation efficiency and solid angle in the concrete 10, and also include γ rays in which the energy due to scattering is reduced. It is the ratio to 2γ / sec release.

  In the present embodiment, the simultaneous measurement unit 31 measures the simultaneous measurement signals in the γ-ray detectors 13 and 23 to obtain the simultaneous measurement count rate.

  That is, as shown in FIG. 3, cobalt 60 (Co-60), which is artificial radioactivity, emits β-rays and then releases 1173 KeV gamma-ray energy, followed by 1333 KeV, as shown in FIG. 3. Releases the energy of gamma rays. As shown in FIG. 4, each of the above-described γ-ray detectors 13 and 23 has potassium 60 as natural radioactivity in addition to signals C1 (1173 KeV) and C2 (by 1333 Kev) of cobalt 60 as artificial radioactivity. Signal K and environmental γ-ray signal B are detected, and noise signal n is detected. Therefore, the simultaneous measurement unit 31 detects one γ-ray emitted from the cobalt 60 by one γ-ray detector 13 at the same time, and the other γ-ray detector 23 detects the remaining γ-rays from the cobalt 60. , The simultaneous measurement unit 31 determines that γ rays from cobalt 60, which is artificial radioactivity, has been detected, and outputs a simultaneous measurement signal C.

Then, the artificial radioactivity calculating unit 32 calculates the gamma ray count rate due to natural radioactivity and the count rate due to environmental gamma rays from the coincidence count rate C due to the gamma rays of cobalt 60 and the count rates of the gamma ray detectors 13 and 23 at this time. The amount of radioactivity Q of Co-60 is calculated from the counting rates Ca and Cb of the cobalt 60 obtained by removing γ.
here,
Ca = Q · ωa · εa
Cb = Q · ωb · εb
Therefore, the coincidence rate C of cobalt 60 by γ rays can be described as follows.
C = Q · ωa · εa · ωb · εb · (1/2)
And the following numerical formula can be calculated | required from the said three numerical formula, By inputting into this numerical formula the count rate Ca and Cb by the gamma ray of cobalt 60, and the coincidence count rate C by the gamma ray of cobalt 60, in concrete 10 The amount Q of artificial radioactivity can be determined.
Q = (Ca · Cb) / 2C

  Thus, in the artificial radioactivity measuring apparatus and measuring method of Example 1, ultrathin flat plate type plastic scintillator detectors 12 and 22 and flat plate type NaI (Tl) scintillator detectors (γ ray detection) are provided on both sides of the concrete 10. A pair of radiation detectors 11 and 21 composed of aluminum cut plates 14 and 24, and a pair of γ-ray detectors, flat NaI (T?) Scintillator detectors 13 and 23. The amount of artificial radioactivity is obtained based on the simultaneous measurement count rate C measured by the simultaneous measurement unit 31 that detects the simultaneously measured signals. In this case, since the concrete 10 has a flat plate shape, the concentration of the natural radioactivity is set based on the detection efficiency based on the counting rates AP and BP of the natural radioactivity β-ray, and the natural radioactivity is determined from the shape measurement data of the concrete 10. The counting rates Ka and Kb by γ rays are obtained.

  Therefore, the natural radioactivity obtained from the count rates Aa and Ab detected by the flat NaI (Tl) scintillator detectors 13 and 23 and the count rates APa and APb detected by the ultrathin flat plastic scintillator detectors 12 and 22 are obtained. Based on the counting rates Ka and Kb by γ rays, the counting rates Ca and Cb by γ rays of cobalt 60 and the simultaneous counting rate C by γ rays of cobalt 60 measured simultaneously are obtained. The amount of radioactivity Q can be obtained, and the incidence ratios ωa and ωb of the artificial radioactivity entering the radiation detection devices 11 and 21 from the concrete 10 and the artificial radioactivity γ rays incident on the radiation detection devices 11 and 21 are obtained. Without directly determining the detection ratios εa and εb, it is possible to determine the amount of artificial radioactivity or the concentration of artificial radioactivity, and as a result, measurement and measurement work with little error in artificial radioactivity. Business can be simplified.

  FIG. 5 is a schematic diagram of an artificial radioactivity measurement apparatus according to Embodiment 2 of the present invention. In addition, the same code | symbol is attached | subjected to the member which has the same function as what was demonstrated in the Example mentioned above, and the overlapping description is abbreviate | omitted.

  As shown in FIG. 5, the artificial radioactivity measuring apparatus according to the second embodiment is arranged on both sides of concrete 40 as a measurement object with the detection surfaces facing the concrete 40, and counting by γ rays emitted from the concrete 40 is performed. A pair of radiation detection devices 41 and 51 for counting the rate, a simultaneous measurement unit (measurement time setting means) 61 for counting signals measured simultaneously by the pair of radiation detection devices 41 and 51, and the simultaneous measurement unit An artificial radioactivity amount calculation unit (artificial radioactivity calculation means) 62 for obtaining an artificial radioactivity amount based on the coincidence counting rate measured by 61 is configured.

  The radiation detection devices 41 and 51 are flat-plate NaI (Tl) scintillator detectors and have count rate calculation units 42 and 52. That is, the radiation detectors (flat-plate NaI (Tl) scintillator detectors) 41 and 51 can capture γ-rays emitted from the concrete 40, and the counting rates Ca and Cb by artificial radioactivity γ-rays and natural It is possible to count the total count rates Aa and Ab, which are the sum of the count rates Ka and Kb due to radioactive γ rays and the count rates GBa and GBb due to environmental background components.

  Then, based on the counting rates Aa and Ab of the radioactive γ rays emitted from the concrete 40 thus obtained, the counting rate calculating units 42 and 52 have the counting rates Ca and Cb of γ rays of cobalt 60 which is artificial radioactivity. Is calculated and output to the artificial radioactivity calculation unit 62.

Here, a method of calculating the count rates Ca and Cb by the cobalt 60 γ rays by the count rate calculation units 42 and 52 will be described. The counting rates Aa and Ab by the radiation detectors 41 and 51 are the counting rates Ka and Kb due to γ rays of natural radioactivity, the counting rates Ca and Cb due to γ rays of artificial radioactivity, and the counting rates GBa due to environmental background components. , GBb are totaled and can be expressed by the following mathematical formula.
Aa = Ka + Ca + GBa
Ab = Kb + Cb + GBb
Here, since what is to be obtained is the counting rates Ca and Cb of the artificial radioactivity (cobalt 60) by γ rays, the above formula is modified.
Ca = Aa-Ka-GBa
Cb = Ab-Kb-GBb

  In this case, prior analysis, that is, the counting rates Ka and Kb of natural radioactivity with γ rays are set according to the shape, weight and composition of the concrete 40.

  Further, in the present embodiment, the simultaneous measurement unit 61 obtains the coincidence counting rate C measured by the simultaneous measurement unit 61 that counts signals measured simultaneously by the radiation detection apparatuses 41 and 51. . Note that the method for simultaneously measuring the coincidence rate C by gamma rays of cobalt 60 is the same as that in the above-described embodiment.

And the artificial radioactivity amount Q in the concrete 40 can be calculated | required by inputting into the following numerical formula count rate Ca, Cb by the gamma ray of cobalt 60, and the total count rate C by the gamma ray of cobalt 60.
Q = (Ca · Cb) / 2C

  Thus, in the artificial radioactivity measurement apparatus and measurement method of Example 2, a pair of radiation detection apparatuses 41 and 51 each including a flat NaI (Tl) scintillator detector are provided on both sides of the concrete 40, and a simultaneous measurement unit The coincidence counting rate is obtained at 61, and the amount of artificial radioactivity is obtained based on the coincidence counting rate. In this case, since the counting rate by the natural radioactivity of the concrete 40 is unknown, the density of the natural radioactivity is obtained by a prior analysis, the natural radioactivity concentration in the concrete is made uniform, and the natural radioactivity concentration is based on the shape of the concrete. Count rates Ka and Kb by γ rays are obtained.

  Therefore, based on the total count rates Aa and Ab detected by the radiation detectors 41 and 51 and the count rates Ka and Kb of γ-rays of natural radioactivity determined by the prior analysis, the count rate Ca, Cb and simultaneous counting rate C of cobalt 60 measured by γ-rays can be obtained, and based on these, the gamma dose Q of artificial radioactivity in concrete 40 can be obtained, and the distribution of artificial radioactivity in concrete is assumed. It is possible to determine the amount of artificial radioactivity or the concentration of artificial radioactivity in concrete without providing a thickness, and as a result, it is possible to measure with high accuracy.

  6-1 is a schematic diagram of an artificial radioactivity measuring apparatus according to Example 3 of the present invention, FIG. 6-2 is a graph showing a coincidence count rate per unit radioactivity with respect to a radioactivity distribution position, and FIG. 1 is a schematic diagram of the artificial radioactivity measurement apparatus of Example 3 corresponding to different concrete shapes, and FIG. 7-2 is a graph showing the coincidence count rate per unit radioactivity with respect to the distribution position of radioactivity. In addition, the same code | symbol is attached | subjected to the member which has the same function as what was demonstrated in the Example mentioned above, and the overlapping description is abbreviate | omitted.

  As shown in FIGS. 6-1 and 7-1, the artificial radioactivity measuring apparatus of Example 3 is counted by γ rays emitted from the concrete 70, 80 on both sides of the concrete 70, 80 as a measurement object. A pair of radiation detection devices 41 and 51 for counting the rate, a simultaneous measurement unit 61 for counting signals measured simultaneously by the pair of radiation detection devices 41 and 51, and a simultaneous measurement by the simultaneous measurement unit 61 It comprises an artificial radiation dose calculation unit 62 for obtaining a count rate and obtaining an artificial radioactivity amount based on the total count rate.

  The radiation detection devices 41 and 51 are flat-plate NaI (Tl) scintillator detectors and have count rate calculation units 42 and 52. That is, the radiation detection devices 41 and 51 can capture γ rays emitted from the concrete 40, and the counting rates Ca and Cb due to γ rays of artificial radioactivity and the counting rates Ka and Kb due to γ rays of natural radioactivity. Then, the total count rates Aa and Ab obtained by adding the count rates GBa and GBb based on the environmental background components can be counted.

  Then, based on the counting rates Aa and Ab due to the γ rays emitted from the obtained concrete 70 and 80, the counting rate calculation units 42 and 52 count the artificial radioactivity, that is, the counting rates Ca and Cb due to the cobalt 60 γ rays. Is output to the simultaneous measurement unit 61 that outputs to the artificial radioactivity calculation unit 62. In addition, the method of calculating | requiring the counting rates Ka and Kb by the gamma ray of natural radioactivity, and the counting rates GBa and GBb by an environmental background component is the same as that of Example 2 mentioned above.

  In addition, the simultaneous measurement unit 61 obtains a simultaneous count rate C that is simultaneously measured by the simultaneous measurement unit 61 that counts signals that are simultaneously measured by the radiation detection apparatuses 41 and 51.

  By the way, in a present Example, concrete 70,80 is not flat shape, but has made a deformed shape, and the distribution state of artificial radioactivity is unknown. However, in the concrete 70, as shown in FIG. 6-2, the artificial radioactivity is uniformly distributed, the artificial radioactivity is distributed in the center, and the artificial radioactivity is on the surface 70a. In the distribution, the simultaneous counting rate per unit radioactivity determined by simultaneous measurement using the radiation detection devices 41 and 51 is approximately the same. Further, in concrete 80, as shown in FIG. 7-2, the artificial radioactivity is uniformly distributed, the artificial radioactivity is distributed on the upper surface 80a, and the artificial radioactivity is on the side surface 80b. The simultaneous count rate per unit radioactivity obtained by simultaneous measurement using the radiation detectors 41 and 51 is approximately the same between the distributed one and the one having the work radioactivity distributed on the lower surface 80c. ing.

Therefore, irrespective of the shape of the concrete 70, 80, the detection efficiency Z _T of the radiation to the radiation detectors 41, 51 is evaluated based on the shape of the concrete assuming that the distribution of the artificial radiation is uniform, This detection efficiency Z _T is set.
Z _T = ωa · ωb · εa · εb · (1/2)
Then, by inputting the detection efficiency Z _T and the coincidence counting rate C of the cobalt 60 by γ rays into the following formula, the γ dose Q of the artificial radioactivity in the concrete 10 can be obtained.
Q = C / Z _T

Thus, in the artificial radioactivity measurement apparatus and measurement method of Example 3, a pair of radiation detection apparatuses 41 and 51 each including a flat NaI (Tl) scintillator detector are provided on both sides of the concrete 70 and 80, and simultaneously. The coincidence counting rate C to be measured set by the measuring unit 61 is obtained, and the artificial radioactivity is obtained based on the coincidence counting rate C. In this case, regardless of the shape of the concrete 70, 80, the detection efficiency Z _T of the simultaneous measurement by the radiation detectors 41, 51 is set based on the concrete shape with the distribution of artificial radioactivity set to be uniform. .

Therefore, based on the detection efficiency Z _T of the simultaneous measurement by the radiation detection devices 41 and 51 and the coincidence counting rate C obtained by the simultaneous measurement of the radiation detection devices 41 and 51, the artificial radioactivity amount Q in the concrete 70 and 800 is calculated. Even if there is no counting rate GBa, GBb or natural radioactivity concentration information due to environmental background components, it is possible to obtain the amount of artificial radioactivity or the concentration of artificial radioactivity, and as a result, in concrete in advance Therefore, it is not necessary to obtain the natural radioactivity concentration, and the measurement work of artificial radioactivity can be simplified.

  The configuration of the artificial radioactivity measurement apparatus according to the fourth embodiment is the same as that of the second embodiment described above, and will be described with reference to FIG. As shown in FIG. 5, the artificial radioactivity measuring apparatus according to the fourth embodiment is arranged with a detection surface facing the concrete 40 on both sides of the concrete 40 and counts the counting rate by γ rays emitted from the concrete 40. Radiation detectors 41 and 51, a simultaneous measurement unit 61 that counts signals measured simultaneously by the pair of radiation detection devices 41 and 51, and a simultaneous count rate that is measured by the simultaneous measurement unit 61. And an artificial radiation dose calculator 62 for obtaining a gamma dose of the artificial radioactivity based on the total count rate.

The radiation detectors 41 and 51 are flat-plate NaI (Tl) scintillator detectors, which have count rates Ca and Cb due to γ rays of artificial radioactivity, count rates Ka and Kb due to γ rays of natural radioactivity, and an environmental bag. The count rates Aa and Ab which are the sum of the count rates GBa and GBb based on the ground components can be counted. In the fourth embodiment, the count rates Aa _-BG and Ab excluding the count rates GBa and GBb based on the environmental background components _-Think about _BG .

That is, as mentioned above,
Aa = Ka + Ca + GBa
Ab = Kb + Cb + GBb
If this equation is transformed, the following equation is obtained.
Aa _-BG = Aa-BGa = Ca + Ka = Qωa · εa + βaS
Ab- _BG = Ab-BGb = Cb + Kb = Qωa · εb + βbS
Here, S is the amount of radioactivity of potassium 40 (which can be calculated from the concentration and the concrete weight) as the natural radioactivity in the concrete 40, and βa and βb are detection efficiencies proportional to the amount of radioactivity of this potassium 40. .

And if cobalt 60 and this potassium 40 as artificial radiation are distributed uniformly in the concrete 40, the following numerical formula will be formed. Here, β ₀ is a proportionality constant, and is a difference in responsiveness in the radiation detection apparatuses 41 and 51 between γ rays due to natural radioactivity and γ rays due to artificial radioactivity.
βa / (ωa · ωb) = βb / (εa · εb) = β ₀
When this formula is applied to the formulas of Aa _-BG and Ab _-BG above,
Aa _-BG = ωa · εa (Q + β ₀ S)
Ab _-BG = _ωb · εb (Q + β ₀ S)
Also,
2C = Q ・ ωa ・ εa ・ ωb ・ εb
And
Aa _−BG · Ab _−BG = (2C / Q) · (Q + β ₀ S) ²
Also,
_{Assuming that} f = (Aa _−BG · Ab _−BG ) / 2C, the artificial radioactivity Q can be obtained from the following formula.

Therefore, the artificial radiation dose calculation unit 62 adds the f (the count rates Aa _-BG and Ab _-BG excluding the count rates GBa and GBb due to the environmental background components) and the simultaneous count rate due to the artificial radioactivity in the concrete 40. By substituting the proportionality constant β ₀ obtained from C and the radioactive quantity S of potassium 40 as the natural radioactivity in the concrete 40, the γ dose Q of the artificial radioactivity in the concrete 40 can be obtained.

As described above, in the artificial radioactivity measurement apparatus and measurement method according to the fourth embodiment, the pair of radiation detection apparatuses 41 and 51 including the thick NaI (Tl) scintillator detectors are provided on both sides of the concrete 40, and the simultaneous measurement unit The coincidence rate C measured by 61 is obtained, and the amount of artificial radioactivity is obtained based on the coincidence rate. In this case, the gamma dose Q of the artificial radioactivity is obtained using the count rates Aa _-BG and Ab _-BG excluding the count rates GBa and GBb due to environmental background components.

Therefore, the coincidence counting rate C of cobalt 60 by the simultaneous measurement detected by the radiation detectors 41 and 51, and the counting rates Aa _-BG and Ab _-BG excluding the counting rates GBa and GBb due to environmental background components, The amount of radioactivity S of potassium 40 as the natural radioactivity in the concrete 40 can be obtained, and the amount of artificial radioactivity Q in the concrete 40 can be obtained based on these, and the amount of artificial radioactivity can be obtained without obtaining the shape data of the concrete 40. Or, the concentration of artificial radioactivity can be obtained, and as a result, there are few errors associated with calculation operations when calculating artificial radioactivity, and measurement can be performed even when the amount of artificial radioactivity is small, thereby simplifying the measurement work of artificial radioactivity. be able to.

  The configuration of the artificial radioactivity measurement apparatus according to the fifth embodiment is the same as that of the second and fourth embodiments described above, and will be described with reference to FIG. As shown in FIG. 5, the artificial radioactivity measuring apparatus according to the fifth embodiment is arranged with a detection surface facing the concrete 40 on both sides of the concrete 40 and counts the counting rate by γ rays emitted from the concrete 40. Radiation detectors 41 and 51, a simultaneous measurement unit 61 that counts signals measured simultaneously by the pair of radiation detection devices 41 and 51, and a simultaneous count rate that is measured by the simultaneous measurement unit 61. It comprises an artificial radiation dose calculation unit 62 for obtaining an artificial radiation dose based on the coincidence rate.

The radiation detectors 41 and 51 are flat-plate NaI (Tl) scintillator detectors, counting rates Ca and Cb due to γ rays of artificial radiation, counting rates Ka and Kb due to γ rays of natural radioactivity, and environmental background. Counting rates Aa and Ab can be counted by summing the counting rates GBa and GBb depending on the components. However, when there is artificial radioactivity other than cobalt 60 in the concrete 40, or the natural radioactivity in the concrete 40 is In the case of unknown, in Example 5, the total radioactivity T in the concrete 40 is obtained from the count rates Aa _-BG and Ab _-BG excluding the count rates GBa and GBb due to environmental background components. The total amount of radioactivity T in the concrete 40 is obtained by, for example, the apparatus of Example 1 described above or the one described in Japanese Patent Application Laid-Open No. 2003-4886.

The radioactivity S in the concrete 40 or the radioactivity S obtained by adding the natural radioactivity and the artificial radioactivity excluding Co-60 (S is the product of the radioactivity concentration and the concrete weight) is as follows: Further, the Co-60 amount Q of artificial radioactivity can be subtracted from the total radioactivity amount T in the concrete 40.
S = TQ
Here, using the measurement method of Example 4 described above,
Aa- _BG · Ab- _BG = (2C / Q) · {(1−β ₀ *) Q + β ₀ * T) ²
Moreover, since the said numerical formula is a quadratic formula about Q, Co-60 quantity Q of the artificial radioactivity in the concrete 40 can be calculated | required. β ₀ * is a proportionality constant.

In addition, when the proportionality constant β ₀ * is a numerical value close to 1, the γ dose Q of the artificial radioactivity in the concrete 40 can also be obtained by the following mathematical formula.
Q = (2C · β * ₀ ² · T ² ) / Aa _-BG · Ab _-BG

  Therefore, the artificial radiation dose calculation unit 62 can obtain the Co-60 artificial radioactivity amount Q in the concrete 40 by substituting each numerical value into the above formulas.

Thus, in the artificial radioactivity measurement apparatus and measurement method of Example 5, a pair of radiation detection apparatuses 41 and 51 each including a flat NaI (Tl) scintillator detector are provided on both sides of the concrete 40, and a simultaneous measurement unit The coincidence rate C measured by 61 is obtained, and the Co-60 amount of artificial radioactivity is obtained based on this coincidence rate. In this case, when there is artificial radioactivity other than cobalt 60 in the concrete 40, or when the amount of natural radioactivity in the concrete 40 is unknown, the total count rate excluding the count rates GBa and GBb due to environmental background components The artificial radioactivity Co-60 quantity Q is obtained after _obtaining the total radioactivity quantity T in the concrete 40 by Aa- _BG and Ab- _BG .

Therefore, the total count excluding the simultaneous count rate C by the gamma ray of cobalt 60 and the count rates GBa and GBb by the environmental background components, which are simultaneously measured based on the total count rates Aa and Ab detected by the radiation detectors 41 and 51. The ratios Aa _-BG and Ab _-BG and the total radioactivity T in the concrete 40 can be obtained, and based on these, the artificial radioactivity Co-60 quantity Q in the concrete 40 can be obtained. Without obtaining, even if natural radioactivity other than cobalt 60 exists in the concrete 40 or the natural radioactivity in the concrete 40 is unknown, the artificial radioactivity or the artificial radioactivity concentration can be obtained. As a result, it is not necessary to evaluate the counting rate due to natural radioactivity from the natural radioactivity concentration in the concrete based on the concrete shape. Small measurement and simplification of measuring operation of can be achieved.

  The artificial radioactivity measurement apparatus and measurement method according to the present invention detects an artificial radiation dose by simultaneous measurement by two detectors, and can be applied to an artificial radioactivity measurement apparatus and method for any kind of measurement object. can do.

It is the schematic of the artificial radioactivity measuring apparatus which concerns on Example 1 of this invention. It is the schematic showing the measuring method of the radiation discharge | released from the concrete by the artificial radioactivity measuring apparatus of Example 1. FIG. 6 is an explanatory diagram for explaining the decay of cobalt 60. FIG. It is a schematic diagram showing the measurement signal waveform input into the artificial radioactivity measuring apparatus of Example 1. It is the schematic of the artificial radioactivity measuring apparatus which concerns on Example 2 of this invention. It is the schematic of the artificial radioactivity measuring apparatus which concerns on Example 3 of this invention. It is a graph showing the coincidence counting rate per unit radioactivity with respect to the distribution position of radioactivity. It is the schematic of the artificial radioactivity measuring apparatus of Example 3 corresponding to a different concrete shape. It is a graph showing the coincidence counting rate per unit radioactivity with respect to the distribution position of radioactivity.

Explanation of symbols

10, 40, 70, 80 Concrete (measurement object)
11, 21, 41, 51 Radiation detection device 12, 22 Ultra-thin plate type plastic scintillator detector (first radiation detector)
13, 23 Flat plate NaI (Tl) scintillator detector (second radiation detector)
14,24 Aluminum cut plate (radiation breaker)
31, 61 Simultaneous measurement unit (simultaneous counting rate measuring means)
32, 62 Artificial radioactivity calculation unit (artificial radioactivity calculation means)

Claims (9)

In an artificial radioactivity measuring device that measures artificial radioactivity in a measurement object containing natural radioactivity,
A pair of radiation detection means arranged on both sides of the measurement object with the detection surface facing the measurement object, and counting a counting rate by γ rays emitted from the measurement object;
Coincidence rate measuring means for measuring signals measured simultaneously by the pair of radiation detecting means;
From the coincidence rate measured by the coincidence rate measuring means and the count rate measured by the pair of radiation measuring means, the artificial radioactivity based on the count rate by the environmental background and the natural radioactivity concentration in the measurement object An artificial radioactivity measuring device comprising: The artificial radioactivity measurement apparatus according to claim 1, wherein the artificial radioactivity calculation means includes count rates Ca and Cb based on artificial radioactivity calculated from two count rates counted by the respective radiation detection means, Based on the simultaneous measurement count rate C counted simultaneously by each radiation detection means, the following formula Q = Ca · Cb / 2C
An artificial radioactivity measuring apparatus characterized in that the γ dose Q of the artificial radioactivity is obtained by The artificial radioactivity measurement apparatus according to claim 1, wherein the radiation detection means includes:
It is arranged with the detection surface facing the measurement object, can capture β-rays emitted from the measurement object, and can transmit γ-rays emitted from the measurement object, and the natural radioactivity A first radiation detector that counts a total counting rate of a counting rate of β-rays, a counting rate of γ rays of the natural radioactivity, and a counting rate of γ rays of the artificial radioactivity,
A detection surface having substantially the same size and shape as the detection surface of the first radiation detector, the detection surface is arranged so as to be positioned on the non-detection surface side of the first radiation detector, and the measurement The gamma rays emitted from the object and transmitted through the first radiation detector can be captured, and the counting rate of the natural radioactivity by γ rays and the counting rate of the artificial radiation by γ rays are summed. A second radiation detector for counting the counting rate;
A blocking surface having substantially the same size and shape as the detection surface of the first radiation detector, and positioned on the detection surface side of the first radiation detector so as to overlap the measurement object with the blocking surface facing An artificial radioactivity measuring apparatus, comprising: a radiation blocker that is arranged and blocks the β-rays of the natural radioactivity emitted from the measurement object.   4. The artificial radioactivity measurement apparatus according to claim 3, wherein the artificial radioactivity calculation means obtains a β-ray count rate in consideration of the contribution of γ rays in the count rate counted by the first radiation detector. The counting rate of the natural radioactivity γ-ray is obtained from the β-ray counting rate according to the detection efficiency, and the natural radioactivity gamma-ray counting rate is calculated from the total counting rate counted by the second radiation detector. An artificial radioactivity measuring apparatus characterized in that a counting rate of the artificial radioactivity by γ rays is obtained by subtracting.   2. The artificial radioactivity measurement apparatus according to claim 1, wherein the radiation detection means is arranged with a detection surface facing the measurement object, capable of capturing γ rays emitted from the measurement object, and the natural radiation. A radiation detector that counts the total counting rate of the gamma ray counting rate and the gamma ray counting rate of the artificial radioactivity, wherein the artificial radioactivity calculation means is counted by the radiation detector An artificial radioactivity measuring apparatus, wherein a count rate of γ rays of the artificial radioactivity is obtained by subtracting a count rate of γ rays of the natural radioactivity set by prior analysis from a count rate.   2. The artificial radioactivity measurement apparatus according to claim 1, wherein the artificial radioactivity calculation unit estimates an incidence ratio of γ rays entering the radiation detection unit from the measurement object from a shape of the measurement object, and the γ The detection efficiency of the radiation detection means is obtained based on the incidence ratio of rays and the detection ratio of γ rays incident on the radiation detection means, and the coincidence counting rate and the detection counted simultaneously by the respective radiation detection means An artificial radioactivity measuring apparatus for obtaining the artificial radioactivity based on efficiency.   The artificial radioactivity measurement apparatus according to claim 1, wherein the artificial radioactivity calculation means obtains a count rate obtained by subtracting a count rate due to an environmental background from two simultaneous count rates counted by the respective radiation detection means, The artificial radioactivity is calculated based on the count rate excluding the environmental background component, the natural radioactivity concentration contained in the concrete, and the simultaneous count rate simultaneously counted by the respective radiation detection means. Radioactivity measuring device.   The artificial radioactivity measurement device according to claim 1, wherein the artificial radioactivity calculation means obtains a count rate obtained by subtracting a count rate due to an environmental background from two simultaneous count rates counted by the respective radiation detection means, The artificial radioactivity is obtained based on the count rate excluding this environmental background component, all the radioactivity contained in the concrete, and the simultaneous count rate simultaneously counted by the respective radiation detection means. Radioactivity measuring device.   The counting rate by the gamma rays emitted from the measurement object is counted by a pair of radiation detection means arranged on both sides of the measurement object, and the coincidence counting rate measured at the same time by the pair of radiation detection means An artificial radioactivity measurement method characterized in that a gamma dose of artificial radioactivity is obtained based on the above.

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