CN117259265A - Method, device, equipment and storage medium for dividing boundary of radioactive substance - Google Patents
Method, device, equipment and storage medium for dividing boundary of radioactive substance Download PDFInfo
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- CN117259265A CN117259265A CN202311401343.4A CN202311401343A CN117259265A CN 117259265 A CN117259265 A CN 117259265A CN 202311401343 A CN202311401343 A CN 202311401343A CN 117259265 A CN117259265 A CN 117259265A
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Abstract
The invention discloses a radioactive substance boundary dividing method, a device, equipment and a storage medium, wherein the method is used for determining a front boundary and a rear boundary through the relation between the radioactivity specific activity of an obtained radioactive substance block and a sorting threshold value, so that contaminated radioactive substances can be ensured to be detected and not to be sorted into uncontaminated radioactive substances, the front boundary of the contaminated radioactive substance block can be determined when the uncontaminated radioactive substances are detected in an uncontaminated state, and the rear boundary of the contaminated radioactive substance block can be determined when the uncontaminated radioactive substances are detected from the contaminated radioactive substances. Is beneficial to improving the sorting efficiency and the sorting precision.
Description
Technical Field
The present invention relates to the technical field of radioactive material sorting, and in particular, to a method, an apparatus, a device and a storage medium for dividing a radioactive material boundary of a radioactive super-threshold radioactive material.
Background
Radioactivity has serious harm to human health, and under the irradiation of high-dose radiation, radioactivity has serious harm to human bodies and animals. Such as 5% deaths in irradiated persons under 400rad (rad, radiation dose absorption intensity units) irradiation; if 650rad is irradiated, the person dies 100%. Even if the irradiation dose is below 150rad, the mortality rate is zero, but the effect is not harmless, and some symptoms are often shown after 20 years. Radioactivity can also damage the dosage unit genetic material, mainly by causing genetic mutations and chromosomal aberrations, causing damage to one or even several generations.
The radioactive material radioactivity monitoring is an important issue for environmental radioactive pollution monitoring, and the radioactive material detection and sorting system can monitor the radioactivity of radioactive materials and sort polluted radioactive materials and uncontaminated radioactive materials.
Before the radioactive substance is fed, the polluted radioactive substance or the uncontaminated radioactive substance is regional coherent, and then the section of the radioactive substance is polluted or the section of the radioactive substance is uncontaminated after being reacted onto the conveyer belt of the equipment, so that the detection sorting state can be simplified into four states:
1. contaminated radioactive material sorting status: finding a non-polluted radioactive substance block in the polluted radioactive substances;
2. switching state 1: the polluted radioactive substances are found to be uncontaminated, and the boundary of the polluted radioactive substances is defined;
3. uncontaminated radioactive material sorting status: finding a polluted radioactive substance block from the uncontaminated radioactive substances;
4. switching state 2: the contaminated radioactive material mass is found in the uncontaminated radioactive material and defines the contaminated radioactive material front boundary.
During the measurement, it is ensured that contaminated radioactive material is detected and not sorted into uncontaminated radioactive material, and therefore, when contaminated radioactive material is detected from uncontaminated conditions, it is necessary to determine the front boundary of the contaminated radioactive material block, and when uncontaminated radioactive material is detected from contaminated radioactive material, it is necessary to determine the rear boundary of the contaminated radioactive material block.
Therefore, how to provide a method for dividing boundaries of radioactive super-threshold radioactive substances is an urgent technical problem to be solved by those skilled in the art.
Disclosure of Invention
In view of the above, the present invention provides a radioactive substance boundary dividing method, apparatus, device and storage medium for overcoming or at least partially solving the above problems. The invention provides the following scheme:
a radioactive material boundary dividing method, apparatus, device and storage medium, including:
determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system, wherein the total length of the n radioactive substance blocks is L;
acquisition of the kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
determining the specific activity of radioactivity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
Obtaining the k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
Determining the specific activity of radioactivity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the kth-S a The radioactive material block is the front boundary of the polluted radioactive material, and Sa is radioactivity specific activity M k A smooth window when the radiometric data is averaged.
Preferably: acquisition of No. i radioactive substance block L i Is not average of radioactivity specific activity M i ' and (i+1) -th radioactive substance block L i+1 Is not average of radioactivity specific activity M i+1 ’；
Determining the specific activity of radioactivity M i ' less than the sorting threshold M L And the radioactivity specific activity M i+1 ' greater than or equal to the sorting threshold M L Determining the ith radioactive substance block as the front boundary of the polluted radioactive substance;
wherein k-S a I is more than or equal to k, and the radioactivity specific activity before the i radioactive substance block is the k+1 radioactive substance block is less than the sorting threshold M L Is the last radioactive material block.
Preferably: determining the kth-S a Determining the kth-S when the distance between the radioactive substance mass and the boundary of the measuring surface of the second detector is greater than L-L a The radioactive material block is the front boundary of the polluted radioactive material; and l is the product of the second detector nuclide identification time and the running speed of the conveyer belt.
Preferably: determining the kth-S a And when the distance between the radioactive substance block and the measuring surface boundary of the second detector is smaller than L-L, determining the radioactive substance block at the position L-L away from the measuring surface boundary of the second detector as the front boundary of the polluted radioactive substance.
Preferably: the second detector is arranged above the upper surface of the conveying belt and is positioned at the rear end of the feeding container of the detection system; the specific activity of radioactivity M k Obtained by the formula:
M k is a radioactive substance block L k Specific activity of radioactivity of A k Is a radioactive substance block L k Total activity of m k Is radioactiveMass L k Is used for the quality of the (a),for the radioactive material mass L measured by the second detector k Net count rate of F t The specific activity of the second detector for the target species is a conversion factor.
Preferably: the detector also comprises a first detector, wherein the first detector and the second detector are plastic scintillator detectors with the same specification; the first detector is arranged above the upper surface of the radioactive substance conveying belt and is positioned at the front end of the feeding container; the radioactive material block L measured by the second detector k Net count rate of (2)Obtained by the formula:
wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb For the background count rate obtained for the first detector, C 1 、C 1 ' is a response calibration factor between the first detector and the second detector.
Preferably: the radioactive material block L measured by the second detector k Net count rate of (2)Obtained by
Wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb Obtained for the first detectorBackground count Rate, C 1 、C 1 ' is the response calibration factor between the first detector and the second detector, < +.>As natural nuclides in radioactive materials 40 Counting rate of K.
A radioactive material boundary partitioning apparatus, comprising:
a radioactive substance block size determining unit for determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system and the total length of the n radioactive substance blocks is L;
radioactive material block L k An radioactivity specific activity obtaining unit for obtaining a kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
A back boundary determining unit for determining the radioactivity specific activity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
radioactive material block L k+1 An radioactivity specific activity obtaining unit for obtaining a k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
A front boundary determining unit for determining the radioactivity specific activity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the kth-S a The radioactive mass is the front boundary of the polluted radioactive material, and the Sa is the radioactivity specific activity M k A smooth window when the radiometric data is averaged.
A radioactive material boundary partitioning apparatus, the apparatus comprising a processor and a memory:
the memory is used for storing program codes and transmitting the program codes to the processor;
The processor is configured to perform the radioactive material boundary partitioning method described above according to instructions in the program code.
A computer readable storage medium for storing a program code for performing the above-described radioactive material boundary dividing method.
According to the specific embodiment provided by the invention, the invention discloses the following technical effects:
according to the radioactive substance boundary dividing method, device, equipment and storage medium, the front boundary and the rear boundary are determined according to the relation between the radioactivity specific activity of the obtained radioactive substance blocks and the sorting threshold, so that contaminated radioactive substances can be ensured to be detected and not to be sorted into uncontaminated radioactive substances, when the uncontaminated state detects the contaminated radioactive substances, the front boundary of the contaminated radioactive substance blocks can be determined, and when the uncontaminated radioactive substances are detected from the contaminated radioactive substances, the rear boundary of the contaminated radioactive substance blocks can be determined. Is beneficial to improving the sorting efficiency and the sorting precision.
Of course, it is not necessary for any one product to practice the invention to achieve all of the advantages set forth above at the same time.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are required to be used in the embodiments will be briefly described below. It is evident that the drawings in the following description are only some embodiments of the present invention and that other drawings may be obtained from these drawings by those of ordinary skill in the art without inventive effort.
FIG. 1 is a flow chart of a method for demarcating boundaries of radioactive materials according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of the relationship between the maximum speed of a conveyor belt and the thickness of radioactive materials according to an embodiment of the present invention;
FIG. 3 is a schematic illustration of the delivery of radioactive materials provided by an embodiment of the present invention;
FIG. 4 is a schematic diagram of a detection system layout according to an embodiment of the present invention;
FIG. 5 is a schematic diagram of a measurement surface of a detection system according to an embodiment of the present invention;
FIG. 6 is a schematic diagram of a radioactive material measurement calculation provided by an embodiment of the present invention;
FIG. 7 is a schematic view of the partitioning of a radioactive material block provided by an embodiment of the present invention;
FIG. 8 shows the forward movement of radioactive material provided by an embodiment of the present inventionA post measurement schematic;
FIG. 9 is a smoothed schematic representation of radiometric measurement of a radioactive material block provided by an embodiment of the present invention;
FIG. 10 is a schematic view of the boundary of a radioactive material after being contaminated by an embodiment of the present invention;
FIG. 11 is a schematic diagram of determining the front boundary of a contaminating radioactive material provided by an embodiment of the present invention;
FIG. 12 is a graph showing the effect of the sodium iodide detector nuclide recognition speed on the accuracy of the separation provided by an embodiment of the present invention;
FIG. 13 is a schematic view of a radioactive material boundary dividing apparatus according to an embodiment of the present invention;
fig. 14 is a schematic view of a radioactive material boundary dividing apparatus according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. It will be apparent that the described embodiments are only some, but not all, embodiments of the invention. All other embodiments, which are derived by a person skilled in the art based on the embodiments of the invention, fall within the scope of protection of the invention.
Referring to fig. 1, a method for dividing boundaries of a radioactive substance according to an embodiment of the present invention, as shown in fig. 1, may include:
s101: determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system, wherein the total length of the n radioactive substance blocks is L;
S102: acquisition of the kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
s103: determining the specific activity of radioactivity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
s104: obtaining the k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
S105: determining the specific activity of radioactivity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the kth-S a The radioactive material block is the front boundary of the polluted radioactive material, and S a For radioactivity specific activity M k A smooth window when the radiometric data is averaged.
The radioactive substance boundary dividing method provided by the embodiment of the application can ensure that the polluted radioactive substance is detected and not sorted into the uncontaminated radioactive substance, and can determine the front boundary of the polluted radioactive substance block when the polluted radioactive substance is detected from the uncontaminated state and determine the rear boundary of the polluted radioactive substance block when the uncontaminated radioactive substance is detected from the polluted radioactive substance. Providing boundary basis for the subsequent radioactive material sorting system.
To further improve the sorting accuracy of the system, embodiments of the present application may also provide for obtaining the ith radioactive material block L i Is not average of radioactivity specific activity M i ' and (i+1) -th radioactive substance block L i+1 Is not average of radioactivity specific activity M i+1 ’；
Determining the specific activity of radioactivity M i ' less than the sorting threshold M L And the radioactivity specific activity M i+1 ' greater than or equal to the sorting threshold M L Determining the ith radioactive substance block as the front boundary of the polluted radioactive substance;
wherein k-S a I is more than or equal to k, and the radioactivity specific activity before the i radioactive substance block is the k+1 radioactive substance block is less than the sorting threshold M L Is the last radioactive material block.
The radioactive substance boundary dividing method provided by the embodiment of the application can be used in a detection system provided with two plastic scintillator detectors and a sodium iodide detector, and the sodium iodide detector can measure nuclide type information and activity ratio information of each nuclide in the radioactive substance block. The kind information of nuclides and the activity ratio information of each nuclide are mapped to the measurement count of the plastic scintillator detector, and the specific activity of each nuclide is measured by the plastic scintillator detector, so that the system measurement requirement is met, and only one sodium iodide detector is used, so that the measurement speed is improved, and the cost is reduced.
In order to eliminate the influence of the output information lag of the sodium iodide detector, the embodiment of the application can also provide the determination of the kth-S a Determining the kth-S when the distance between the radioactive substance mass and the boundary of the measuring surface of the second detector is greater than L-L a The radioactive material block is the front boundary of the polluted radioactive material; and l is the product of the second detector nuclide identification time and the running speed of the conveyer belt.
Further, the kth-S is determined a When the distance between the radioactive substance mass and the boundary of the measuring surface of the second detector is less than L-LThe radioactive material mass at a location L-L from the measuring surface boundary of the second detector is determined as the front boundary of the contaminating radioactive material.
It will be appreciated that the specific activity of each radioactive material block provided in the embodiments of the present application may be obtained using any of the methods of measuring specific activity of radioactive material blocks available in the art. For example, in one implementation, embodiments of the present application may provide that the second detector is disposed above an upper surface of the conveyor belt and at a rear end of a supply vessel of the detection system; the specific activity of radioactivity M k Obtained by the formula:
M k Is a radioactive substance block L k Specific activity of radioactivity of A k Is a radioactive substance block L k Total activity of m k Is a radioactive substance block L k Is used for the quality of the (a),for the radioactive material mass L measured by the second detector k Net count rate of F t The specific activity of the second detector for the target species is a conversion factor.
In order to facilitate subtraction of background data of a second detector, the embodiment of the present application may further provide a first detector, where the first detector and the second detector are plastic scintillator detectors of the same specification; the first detector is arranged above the upper surface of the radioactive substance conveying belt and is positioned at the front end of the feeding container; the radioactive material block L measured by the second detector k Net count rate of (2)Obtained by the formula:
wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb For the background count rate obtained for the first detector, C 1 、C 1 ' is a response calibration factor between the first detector and the second detector.
In order to obtain the net count rate of the second detector, the embodiment of the application can also provide the radioactive substance mass L measured by the second detector k Net count rate of (2)Obtained by the formula:
wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb For the background count rate obtained for the first detector, C 1 、C 1 ' is the response calibration factor between the first detector and the second detector, < +.>As natural nuclides in radioactive materials 40 Counting rate of K.
It will be appreciated that the above method describes a radioactive material block L k The specific activity M of (2) k The (k+1) th radioactive substance block L k+1 The specific activity M of (2) k+1 Method for obtaining (1) and radioactive material block L k The specific activity M of (2) k The acquisition method is the same and will not be described in detail here.
The radioactive substance is detected under the condition that the detection efficiency of the radioactive substance reaches 118-122t/h 137 For the radiation detection system with the Minimum Detectable Activity (MDA) of Cs reaching 98-105Bq/kg, the embodiment of the application is providedThe method of dividing the boundary of the radioactive substance will be described in detail.
In practical application, the detection area of the plastic scintillator detector can be 100cm×50cm, the width of the radioactive substance carried by the radioactive substance conveying belt can also be 100cm, that is, the width of the radioactive substance conveying belt is equal to the length of the plastic scintillator, both the widths are 1m, and the length of the plastic scintillator detector in the transmission direction of the radioactive substance can be 50cm. The sorting efficiency m (t/h) of the radioactive substance and the thickness h (cm) of the radioactive substance, the speed v (m/s) of the conveyor belt and the density ρ (g/cm) of the radioactive substance 3 ) The relation between the two is:
the density of the loose radioactive material is generally 0.5g/cm 3 ～1.8g/cm 3 The density of the radioactive substance taken in the examples of the present application is 1.5g/cm 3 The above formula becomes:
m＝54vh (2)
if the sorting efficiency m of the radioactive substance reaches 118-122 tons/hour, the relation between the thickness of the radioactive substance and the maximum speed of the conveyor belt is shown in fig. 2, and the point selected in the actual operation should fall on the shaded portion of the figure.
The thickness of the radioactive material on the conveyor was determined to be 7cm at maximum, and the minimum speed of the conveyor at this time was 0.32m/s as seen from the formula (2).
The length L of the radioactive substance below the plastic scintillator drop is 0.5m in the conveying direction of the conveyor belt, as shown in fig. 3.
When the plastic scintillator detector is used, the measuring surface of the plastic scintillator detector is as close to the surface of the radioactive substance block as possible, and the area of the measuring area of the detector on the radioactive substance is 100cm multiplied by 50cm through lead shielding. The sodium iodide detector was also collimated by lead to give a measurement area of 100cm by 50cm on the radioactive material.
The time for the radioactive material at a point on the conveyor belt to pass through the measuring area of the detectors, i.e., the time for each detector to measure the radioactivity at a point in the radioactive material is at most only 1.56 seconds.
Because the response time of the plastic scintillator detector is very fast, and is usually in nanosecond level, the measurement time of 1.56 seconds is relatively abundant, the larger detection area and the longer measurement time are beneficial to reducing the minimum detectable activity of the detector, so the radiation detection system can be provided with a plastic scintillator detector with the size of 100cm multiplied by 50cm multiplied by 5cm, and the plastic scintillator detector is cheaper, and meanwhile, for better background subtraction, the background radiation value measurement can be specially carried out by using a plastic scintillator detector with the same size in the radiation detection system.
It is understood that plastic scintillators are one of the organic scintillators, which mainly include anthracene crystals, liquid scintillators, plastic scintillators. The plastic scintillator is a solid-solid body of organic scintillating material in plastic, and is generally composed of matrix scintillating material and wave-shifting agent. The matrix material is mainly a scintillating substance such as polystyrene, and the wave shifter has the function of effectively and rapidly transmitting and prolonging the scintillating light. The plastic scintillator is not a crystal, but is an organic scintillator, and can be used for detecting various radioactive rays.
It can be seen that the plastic scintillator detector, although measuring time is fast, has poor energy resolution because it measures the energy of the optical signal, and there is some loss in the propagation of the optical signal, thus causing attenuation of the signal and an increase in noise. This makes scintillator detectors inadequate for some experimental requirements with high energy resolution requirements. Therefore, the plastic scintillator detector cannot identify nuclides and cannot meet the system requirements, and therefore, the sodium iodide detector is also required to be configured in the embodiment of the application.
The Nal (TI) scintillator belongs to one of inorganic scintillators, and the inorganic scintillators comprise Nal (TI) scintillators, csl (TI) scintillators, CLYC scintillators and the like, and other inorganic crystals (such as cadmium tungstate, bismuth germanate and the like) and even glass bodies. Among the most widely used are Nal (TI) scintillator detectors (Nal (TI) crystals). The resolution of the Nal (TI) scintillator is high, and the Nal (TI) scintillator can be used for measuring X and gamma dose rates, and can also be mounted in a nuclide identification device for analyzing energy spectrum and identifying the species of nuclides. The scintillation decay time of a Nal (TI) scintillator is not as short as that of a plastic scintillator, i.e. a device employing a Nal (TI) scintillator does not respond as fast as a device employing a plastic scintillator, and therefore a Nal (TI) scintillator is more suitable for use in applications where sensitivity requirements are higher and response speed requirements are less high than for a plastic scintillator, such as radiation detection of a stable radiation source or a continuously operated radiation device, radiation monitoring of a lower level dose rate in the environment, or applications where both dose rate and energy spectrum are required.
It can be seen that the nuclide identification time of the sodium iodide detector is relatively long, and a few minutes or even longer is required by adopting the conventional nuclide identification method, while the identification time of the sodium iodide detector is further shortened with the development of technology, however, a relatively fast nuclide identification method studied in recent years also requires about 5 seconds.
Therefore, if only sodium iodide detectors are used, a better measurement result is obtained within 1.56 seconds, and a plurality of sodium iodide detectors are needed to be used for common measurement, which is also a method used in a large radioactive substance detection and sorting system currently used at home and abroad, but the method adopting a plurality of sodium iodide detectors has higher cost because of the high price of the large sodium iodide detectors, and has no advantages in engineering application and commercial popularization.
In practical engineering application, the distribution of nuclides in radioactive substances is continuously changed in a large area, and the distribution of nuclides in a certain range is relatively stable, and in practical construction, radioactive substances are continuously obtained from a polluted area and sent to a radioactive substance detection and sorting system, so that the distribution of nuclides of radioactive substances conveyed on a radioactive substance conveying belt can be considered to be relatively stable in a certain distance range.
Based on the analysis, the embodiment of the application can determine that the nuclide identification time of the sodium iodide detector is t I The distance travelled by the radioactive material on the conveyor during this time (e.g. the radioactive material block of length l in fig. 3) is:
l＝vt I (3)
In practical applications, the distribution of nuclides within a radioactive material block of length L (L > L) can be considered to be uniform, then a sodium iodide detector can be used at t I And measuring nuclide type information and activity ratio information of each nuclide in the radioactive substance block in time. And then, the type information of the nuclides and the activity ratio information of each nuclide are mapped into the measurement count of the plastic scintillator detector by adopting a certain method, so that the specific activity of each nuclide can be measured by using the plastic scintillator detector, thereby meeting the system measurement requirement.
Based on the analysis, the radiation detector system of the radioactive substance detection and sorting system consists of three detectors, wherein 2 plastic scintillator detectors (a first detector D1 and a second detector D2) and 1 sodium iodide (Nal) detector (a third detector D3) with the same specification are adopted, the detectors are all placed on the upper surface of a radioactive substance conveying belt, and meanwhile, the non-measurement surface of each detector is subjected to lead shielding so that the effective detection area of each detector is the same, and the arrangement of the detectors of the system is shown in fig. 4. The radiation detection system consists of three detectors, and the specific activity of each nuclide in the radioactive substance can be obtained by fusing the measurement data of the three detectors in the actual use process.
In the actual detection process, the radioactive substances are evenly spread on the conveying belt through the feeding container and the thickness adjusting baffle knife, the thickness of the radioactive substances can be adjusted between 2 cm and 7 cm according to the needs, the width of the conveying belt can be 1m, and the highest speed of the conveying belt is larger than 0.5m/s. The measurement area of the three detectors on the conveyor belt was 100cm×50cm, as shown in fig. 5.
In practical applications, the installation positions of the sensors may be arranged according to practical use conditions, for example, in one implementation manner, the embodiments of the present application may provide the following arrangement manners:
the D1 detector is arranged at the front end of the feeding container, measures the space background radiation value and the conveyor belt contamination background radiation value on line in real time, and monitors whether the conveyor belt is contaminated beyond standard.
And D3, detecting and identifying target nuclides in the radioactive substance by using a detector, and calculating activity ratio information of each nuclide.
The D2 detector is arranged at the rear end of the feeding container and is used for measuring the total radioactivity of the radioactive substance to be measured. The method is fused with the data of the D1 detector, so that the measurement interference of the background radiation value to the D2 detector is effectively reduced. Meanwhile, the method acquires the activity ratio information of the target nuclide measured by the D3 detector, calculates the contribution ratio of the target nuclide in the radioactive substance to be measured in real time in the radiation net counting rate of the D2 detector through correction and conversion, and finally calculates the target nuclide in the radioactive substance (such as 137 Cs) as shown in fig. 6.
It can be appreciated that, the three detectors provided in the embodiments of the present application are composed of two different types of detectors, and because the gamma-ray detection efficiency of the different types of detectors for different energies is different, when the sodium iodide detector and the plastic scintillator detector perform data fusion, the adverse effect caused by this factor needs to be considered, and the conversion factor between the two types of detectors for different energy rays needs to be measured, so that the influence of the detection efficiency is not ensured when the data fusion is performed.
For this reason, the embodiment of the application provides a method for data fusion of a radiation detector, which is used for data fusion, and the implementation can be performed in the following manner.
Since the length l=50 cm of the detection surface of each detector in the direction of transport of the radioactive material, the velocity of the conveyor belt can be determined to be v 1 Then for a certain radioactive material perpendicular section along the conveying direction, the total measuring time of the detector is A t ＝L/v 1 Determining the update time (i.e. single measurement time) of the detector as R t Every time an elapsed time R t The radioactive material moves forward on the conveyor belt a distance, notedThe radioactive material blocks in the detection surface below the detector can be divided into n parts in the transmission direction, and each small block is placed The length of the radioactive substance is->Then->As shown in fig. 7, the solid represents contaminated radioactive material, and the hollow represents uncontaminated radioactive material.
For a detection in-plane length ofIs determined to be m by mass per small radioactive substance i (i=1, 2,..n) (kg) of radioactivity specific activity M': i (i=1, 2,..n) (Bq/kg), determining the count rate of the small piece of radioactive material measured by the detector as D'; i (i＝1，2，...n)(cps)。
every time the radioactive material advancesThe detector can obtain real-time measurement data D' k (k=1, 2,3 …) (cps), i.e. the count rate of radioactive material measured by the detector per real time is expressed by the following formula:
then the value (D' k N), i.e. real-time measurement data of the radioactive substance small block marked k (but in fact D k Also containing the radiation information of the latter n-1 radioactive material patches) as shown in fig. 9.
In FIG. 9, a radioactive substance block having a length L in the detection plane in this state is labeled L k D 'then' k Namely L k For example, the 1 st measurement D 'of the detector' 1 Marked L for length L in fig. 8 1 Is passed through R t After a while, the radioactive material moves forwardThe radioactive substance block 1 moves out of the measuring area, the radioactive substance block 2 reaches the measuring area boundary of the detector, and the radioactive substance block (n+1) enters the measuring area, the detector completes the 2 nd measurement, and the measured value D 'is measured at the moment' 2 The radioactive material block L with length L marked 2 in FIG. 8 2 Is a counter to the counting rate of (a).
In order to improve robustness and inhibit statistical fluctuation, a real-time measurement value is not directly adopted as a judgment basis, but the current data is smoothed according to the preamble real-time data of the current data, and a sliding window is determined to be S in the smoothing process a Then the current radioactive material block L k The radiation measurement data is given as a formula (5), and the measurement schematic diagram is shown in fig. 9.
Measurement value D k The radiation information of n+Sa radioactive material blocks is actually contained.
For the sodium iodide detector (D3), in practical application, the value of n is related to the length of L in the formula (3), so that the length of n small radioactive substance blocks is equal to the length of L, and the data acquisition method is the same as that described above.
Each time the measurement time R passes t Each detector in the radiation detection system obtains a measured value D' k And D k The system uses the following for each detector measurement:
for the D1 detector:
using the last real-time measurement D' 1k Monitoring the working state of the detector; average measurement value D 1k Background radiation values are measured and the contamination of the conveyor belt is monitored.
For the D2 detector:
using the last real-time measurement D' 2k Monitoring the working state of the detector; average measurement value D 2k The radioactive material contamination level is measured after fusion with other detector data.
For the D3 detector:
using the last real-time measurement D' 3k Monitoring the working state of the detector;
average measurement value D 3k For activity duty cycle analysis of each species in a radioactive material.
After the radiation detection system is started, as can be seen in fig. 4, the radioactive material on the conveyor belt passes through the D2 detector and then the D3 detector. Determining the elapsed time t 1 (k R' s t ) After that, the D2 detector measures the radioactive material block L k Is D 2k At the same time, the D1 detector measures the background radiation value as D 1k After time t2, the D3 detector detects the radioactive substance mass L k Is D 3k 。
The D2 detector subtracts the background radiation value from the D1 detector. Because both detectors are plastic scintillator detectors, the measurement response to the same nuclear species is consistent, but because of the differences of the two detector crystals, photomultiplier tubes, nuclear electronics and the like, the two detectors measure the background radiation values of the same environment to have numerical differences, and the differences need to be considered when data are fused.
The calculation formula of the radiation net count rate of the radioactive substance measured by the D2 detector is as follows:
Wherein,a net count rate of radiation (cps) for the radioactive material measured by the D2 detector; d (D) 2k Total count rate of radiation (cps) for the radioactive material measured by the D2 detector; d (D) 2kb Is the background value of the D2 detector.
The background radiation value of the D2 detector is given by the D1 detector:
D 2kb ＝C 1 D 1kb +C 1 ′ (7)
wherein D is 1kb For the background count rate (cps) measured by the D1 detector, C 1 、C 1 ' D1, D2 detectorAnd the response calibration factor is used for equivalent calculation of the measured values of the D1 and D2 detectors.
The net count rate of radiation of the radioactive substance measured by the D2 detector obtained by combining the formula (6) and the formula (7) is as follows:
when only the target nuclide or other nuclides in the radioactive substance are negligible, the specific activity value of the radioactivity of the radioactive substance, namely the ratio of the radioactivity of the radioactive source to the mass thereof, namely the radioactivity of a certain nuclide contained in a unit mass product, can be obtained by calling the specific activity conversion factor of the target nuclide relative to the D2 detector under different thicknesses/densities of the radioactive substance (specific activity). Radioactive material block L k The specific activity of (c) is calculated from the following formula:
m in the above k Is a radioactive substance block L k Radioactivity specific activity (Bq/g). A is that k Is a radioactive substance block L k Total activity (Bq), m k Is a radioactive substance block L k The mass (g) of (a) is,for the radioactive material mass L measured by the detector k Net count rate (cps), F t The specific activity of the D2 detector to the target nuclide is converted into a factor (g.cps/Bq).
During the measurement, it is ensured that contaminated radioactive material is detected and not sorted into uncontaminated radioactive material, and therefore, when contaminated radioactive material is detected from uncontaminated conditions, it is necessary to determine the front boundary of the contaminated radioactive material block, and when uncontaminated radioactive material is detected from contaminated radioactive material, it is necessary to determine the rear boundary of the contaminated radioactive material block.
From the formula (9), a radioactive material block L can be obtained k The specific activity M of (2) k The specific activity value is also the radioactivity specific activity of the k-th radioactive material pellet. Setting a sorting threshold value as M L When M k ≥M L In this case, it is determined that the detection of the contaminated radioactive material is started, and it is necessary to sort out the radioactive material.
To ensure that no contaminated radioactive material is sorted to uncontaminated radioactive material, the initial state of the system defaults to a contaminated sorting state, as shown in fig. 7, with the discharge port of the sorting hopper on the side of the radioactive material. In order to determine the rear boundary of the contaminating radioactive material, consideration is given to the case of transformation, i.e. the measured value M of the radiation when the length of the contaminating radioactive material in the radioactive material on the conveyor belt is less than or equal to L k ≥M L When the time Rt passes, the radioactive material advances in the moving directionAfter that, its radiation measurement value M k+1 ＜M L The state at this time is shown in fig. 10.
At this time, it was confirmed that the true specific activity of the (k+n) -th radioactive substance pellet was surely smaller than M L Accordingly, the radioactive material pellet (k+n-1) can be marked as the rear boundary of the contaminated radioactive material, at which time the sorting mode is changed from the contaminated sorting mode to the uncontaminated sorting mode. When the radioactive substance small block (k+n-1) reaches the outlet of the sorting hopper through the conveyer belt and flows out, the outlet of the sorting hopper swings to the side of uncontaminated radioactive substance.
In the uncontaminated radioactive material sorting state, the system needs to determine the front boundary of the radioactive material when contaminated radioactive material passes through the detector. When the length of the uncontaminated radioactive material in the measuring surface of the detector on the conveyer belt is less than or equal to L, the radiation measured value M of the uncontaminated radioactive material is determined k ＜M L When the time R passes t The radioactive material advancing in the direction of movementAfter that, its radiation measurement value M k+1 ≥M L At this time, the state is as shown in fig. 11.
Due to M k ＜M L And M is k+1 ≥M L The radioactivity specific activity of the (k+n) th radioactive material pellet can be determined to be supra-threshold, but the principle of detection is to ensure that none of the supra-threshold radioactive material pellet is misclassified into uncontaminated radioactive material. Due to M k Comprises the components numbered from (k+n-1) to (k-S) a ) The radioactive material patch (k+n-1) and the preceding partial radioactive material patch are not completely determined to be uncontaminated. But can determine the radioactive material small block (k-S a ) Is below a threshold value, so that the radioactive material pieces (k-S a ) As the front boundary for contaminating radioactive material.
However, it is determined that the system has a relatively coarse accuracy in sorting radioactive materials, and in practical applications, in order to further improve the sorting accuracy of the system, based on the above criteria, obtaining M is adopted according to empirical values k+1 Last before less than M L Is not smooth M' 1 The value is taken as the judgment basis, M' 1 Is a radioactive substance block L i Not average specific activity of (C), i.e. when M' 1 ＜M L And M' i+1 ≥M L (k-S a I.ltoreq.k), the radioactive material small block denoted by i is taken as the front boundary of the contaminated radioactive material, and in practice, the sorting accuracy of the system is further improved.
The length l of the sodium iodide detector for completing the identification of the nuclide to be measured also affects the sorting accuracy because l is larger than the length of the measuring surface of the detector in the transmission direction, when the target nuclide is present in the radioactive substance and the activity exceeds the threshold value, since the time of the sodium iodide detector for giving information is relatively delayed (the nuclide identification time of the sodium iodide detector is relatively long), when the forefront radioactive substance small block in the radioactive substance contaminating the threshold value has been separated from the measuring boundary (l-50) cm of the detector, the time of determining the front boundary of the radioactive substance contaminated in fig. 11, if the radioactive substance small block (k-S) a ) If the distance from the boundary of the measuring surface of the detector is smaller than (l-50) cm, the radioactive substance small block at (l-50) cm should be used as pollution radioactivityThe front boundary of the material is shown in fig. 12. The influence of the back boundary of the polluted radioactive substance is mainly that the back boundary is prolonged, and the polluted radioactive substance is not scratched into the uncontaminated radioactive substance. Therefore, the method can be used for improving the nuclide identification speed of the sodium iodide detector, shortening the value of l and being beneficial to improving the sorting precision of radioactive substances.
In summary, the radioactive substance boundary dividing method provided by the application can ensure that the radioactive substance with pollution is detected and not sorted into the uncontaminated radioactive substance by determining the front boundary and the rear boundary according to the relation between the radioactivity specific activity of the obtained radioactive substance block and the sorting threshold value, and can determine the front boundary of the polluted radioactive substance block when the uncontaminated radioactive substance is detected from the polluted radioactive substance and determine the rear boundary of the polluted radioactive substance block when the uncontaminated radioactive substance is detected from the polluted radioactive substance. Is beneficial to improving the sorting efficiency and the sorting precision.
Referring to fig. 13, an embodiment of the present application may further provide a radioactive material boundary dividing apparatus, as shown in fig. 13, which may include:
A radioactive substance block size determining unit 1301 configured to determine that n radioactive substance blocks are included on a conveyor belt vertically below the second detector in the detection system and a total length of the n radioactive substance blocks is L;
radioactive material block L k An radioactivity specific activity obtaining unit 1302 for obtaining a kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
a back boundary determination unit 1303 for determining the radioactivity specific activity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
radioactive material block L k+1 An radioactivity specific activity obtaining unit 1304 for obtaining a k+1th radioactive substance block L k+1 The specific activity M of (2) k+1 ；
A front boundary determining unit 1305 for determining the radioactivity specific activity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the kth-S a The radioactive material block is the front boundary of the polluted radioactive material, and S a For radioactivity specific activity M k A smooth window when the radiometric data is averaged.
Embodiments of the present application may also provide a radioactive material boundary dividing apparatus, including a processor and a memory:
the memory is used for storing program codes and transmitting the program codes to the processor;
the processor is configured to perform the steps of the radioactive material boundary partitioning method described above according to instructions in the program code.
As shown in fig. 14, a radioactive substance boundary dividing apparatus provided in an embodiment of the present application may include: a processor 10, a memory 11, a communication interface 12 and a communication bus 13. The processor 10, the memory 11 and the communication interface 12 all complete communication with each other through a communication bus 13.
In the present embodiment, the processor 10 may be a central processing unit (Central Processing Unit, CPU) and a Neural Network Processor (NPU), an asic, a field programmable gate array, or other programmable logic device, etc.
The processor 10 may call a program stored in the memory 11, and in particular, the processor 10 may perform operations in an embodiment of the radioactive substance boundary dividing method.
The memory 11 is used for storing one or more programs, and the programs may include program codes, where the program codes include computer operation instructions, and in this embodiment, at least the programs for implementing the following functions are stored in the memory 11:
determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system, wherein the total length of the n radioactive substance blocks is L;
acquisition of the kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
determining the specific activity of radioactivity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
obtaining the k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
Determining the specific activity of radioactivity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the kth-S a The radioactive material block is the front boundary of the polluted radioactive material, and S a For radioactivity specific activity M k A smooth window when the radiometric data is averaged.
In one possible implementation, the memory 11 may include a storage program area and a storage data area, where the storage program area may store an operating system, and application programs required for at least one function (such as a file creation function, a data read-write function), and the like; the store data area may store data created during use, such as initialization data, etc.
In addition, the memory 11 may include high-speed random access memory, and may also include non-volatile memory, such as at least one magnetic disk storage device or other volatile solid-state storage device. The communication interface 12 may be an interface of a communication module for interfacing with other devices or systems.
Of course, it should be noted that the structure shown in fig. 14 does not limit the radioactive material boundary dividing apparatus in the embodiment of the present application, and the radioactive material boundary dividing apparatus may include more or less components than those shown in fig. 14 or may combine some components in practical applications.
Embodiments of the present application may also provide a computer readable storage medium for storing a program code for performing the steps of the above-described radioactive material boundary dividing method.
It is noted that relational terms such as first and second, and the like are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Moreover, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising one … …" does not exclude the presence of other like elements in a process, method, article, or apparatus that comprises the element.
From the description of the embodiments above, it will be apparent to those skilled in the art that the present application may be implemented in software plus the necessary general hardware platform. Based on such understanding, the technical solutions of the present application may be embodied essentially or in a part contributing to the prior art in the form of a software product, which may be stored in a storage medium, such as a ROM/RAM, a magnetic disk, an optical disk, etc., including several instructions to cause a computer device (which may be a personal computer, a server, or a network device, etc.) to perform the methods described in the embodiments or some parts of the embodiments of the present application.
In this specification, each embodiment is described in a progressive manner, and identical and similar parts of each embodiment are all referred to each other, and each embodiment mainly describes differences from other embodiments. In particular, for a system or system embodiment, since it is substantially similar to a method embodiment, the description is relatively simple, with reference to the description of the method embodiment being made in part. The systems and system embodiments described above are merely illustrative, wherein the elements illustrated as separate elements may or may not be physically separate, and the elements shown as elements may or may not be physical elements, may be located in one place, or may be distributed over a plurality of network elements. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment. Those of ordinary skill in the art will understand and implement the present invention without undue burden.
The foregoing description is only of the preferred embodiments of the present invention and is not intended to limit the scope of the present invention. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention are included in the protection scope of the present invention.
Claims (10)
1. A method of demarcating a boundary of a radioactive substance, comprising:
determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system, wherein the total length of the n radioactive substance blocks is L;
acquisition of the kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
determining the specific activity of radioactivity M k Greater than or equal to sorting threshold M L And the length of the polluted radioactive substances in the radioactive substance block is less than or equal to the length of the radioactive substances vertically below the second detectorL is time; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
obtaining the k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
Determining the specific activity of radioactivity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the radioactive substance mass of the k-Sa as the front boundary of the polluted radioactive substance, wherein Sa is the radioactivity specific activity M k A smooth window when the radiometric data is averaged.
2. The method of demarcating a boundary of a radioactive substance according to claim 1, wherein the i-th radioactive substance block L is obtained i Is not average of radioactivity specific activity M i ' and (i+1) -th radioactive substance block L i+1 Is not average of radioactivity specific activity M i+1 ′；
Determining the specific activity of radioactivity M i ' less than the sorting threshold M L And the radioactivity specific activity M i+1 ' greater than or equal to the sorting threshold M L Determining the ith radioactive substance block as the front boundary of the polluted radioactive substance;
wherein k-Sa is less than or equal to i and less than or equal to k, and the radioactivity specific activity before the ith radioactive substance block is the (k+1) radioactive substance block is less than the sorting threshold M L Is the last radioactive material block.
3. The method of claim 1, wherein when it is determined that the k-Sa radioactive substance block is greater than L-L from the boundary of the measuring surface of the second detector, determining the k-Sa radioactive substance block as the front boundary of the contaminated radioactive substance; and l is the product of the second detector nuclide identification time and the running speed of the conveyer belt.
4. A method of demarcating a radioactive material boundary according to claim 3, wherein when it is determined that the k-Sa radioactive material block is less than L-L from the boundary of the second detector measurement surface, the radioactive material block at the L-L position from the boundary of the second detector measurement surface is determined as the front boundary of the contaminated radioactive material.
5. The method of claim 1, wherein the second detector is disposed above an upper surface of the conveyor belt and at a rear end of a supply vessel of the detection system; the specific activity of radioactivity M k Obtained by the formula:
M k is a radioactive substance block L k Specific activity of radioactivity of A k Is a radioactive substance block L k Total activity of m k Is a radioactive substance block L k Is used for the quality of the (a),for the radioactive material mass L measured by the second detector k Net count rate of F t The specific activity of the second detector for the target species is a conversion factor.
6. The method of claim 5, further comprising a first detector, wherein the first detector and the second detector are plastic scintillator detectors of equal gauge; the first detector is arranged above the upper surface of the radioactive substance conveying belt and is positioned at the front end of the feeding container; the radioactive material block L measured by the second detector k Net count rate of (2)By passing throughThe following formula is obtained:
wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb For the background count rate obtained for the first detector, C 1 、C 1 ' is a response calibration factor between the first detector and the second detector.
7. The method of demarcating a boundary of a radioactive substance according to claim 6, wherein the radioactive substance mass L measured by the second detector k Net count rate of (2)Obtained by the formula:
wherein:for net count rate of radioactive material, D 2k For the total count rate, D 1kb For the background count rate obtained for the first detector, C 1 、C 1 ' is the response calibration factor between the first detector and the second detector, < +.>As natural nuclides in radioactive materials 40 Counting rate of K.
8. A radioactive material boundary dividing apparatus, comprising:
a radioactive substance block size determining unit for determining that n radioactive substance blocks are contained on a conveyor belt vertically below a second detector in the detection system and the total length of the n radioactive substance blocks is L;
radioactive material block L k An radioactivity specific activity obtaining unit for obtaining a kth radioactive substance block L k The specific activity M of (2) k The method comprises the steps of carrying out a first treatment on the surface of the The radioactive material block L k To remove a first block of radioactive material vertically below the second detector;
a back boundary determining unit for determining the radioactivity specific activity M k Greater than or equal to sorting threshold M L And when the length of the polluted radioactive substances in the radioactive substance blocks is smaller than or equal to the length L of the radioactive substances vertically below the second detector; determining the k+n-1 radioactive substance block as the rear boundary of the polluted radioactive substance, wherein the sum of the lengths from the k+n radioactive substance block to the k+1 radioactive substance block is L;
Radioactive material block L k+1 An radioactivity specific activity obtaining unit for obtaining a k+1st radioactive substance block L k+1 The specific activity M of (2) k+1 ；
A front boundary determining unit for determining the radioactivity specific activity M k Less than sorting threshold M L The radioactivity specific activity M k+1 Greater than or equal to sorting threshold M L And when the length of the uncontaminated radioactive substance in the measuring surface of the second detector is less than or equal to L; determining the radioactive substance mass of the k-Sa as the front boundary of the polluted radioactive substance, wherein Sa is the radioactivity specific activity M k A smooth window when the radiometric data is averaged.
9. A radioactive material boundary partitioning apparatus, the apparatus comprising a processor and a memory:
the memory is used for storing program codes and transmitting the program codes to the processor;
the processor is configured to perform the radioactive material boundary partitioning method of any one of claims 1-7 according to instructions in the program code.
10. A computer readable storage medium for storing a program code for performing the radioactive material boundary partitioning method of any one of claims 1-7.
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