CN113706961A - Simulated gamma radiation source searching training system and searching method thereof - Google Patents
Simulated gamma radiation source searching training system and searching method thereof Download PDFInfo
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Abstract
The invention relates to a simulated gamma radioactive source search training system and a search method thereof, the system comprises a simulated nuclear radiation monitor, a simulated gamma radioactive source and a simulated radioactive source parameter setting device, the monitor comprises a microcomputer, a global positioning module, an alarm display module, a power supply module and a wireless communication interface, the radioactive source comprises a microcomputer, a global positioning module, a power supply module and a wireless communication interface, and the parameter setting device comprises a parameter setting module, a power supply module and a wireless communication interface. The searching method based on the system is that the microcomputer in the monitor calculates the distance between the monitor and the source by using the positioning information of the monitor and the radioactive source, and substitutes the positioning information together with the radioactivity activity, the air kerma rate constant and the air line attenuation coefficient of the prestored nuclide into a formula to calculate the dose rate value, and the dose rate is increased when the distance is reduced, and finally the radioactive source is found. The invention simulates gamma radioactive source as harmless source and replaces 'actual measurement' with 'calculation' result.
Description
Technical Field
The invention belongs to the technical field of nuclear radiation monitoring, and particularly relates to a simulated gamma radiation source searching training system and a searching method thereof.
Background
With the development of nuclear science and technology, radioactive sources are widely used in various fields such as science and technology, industry, agriculture, medical treatment, national defense and the like, and the quantity of the radioactive sources rapidly increases at a speed of over ten percent each year. Accidents of radioactive source loss often occur during the development, use, storage and transportation of radioactive sources. The problem that nuclear safety and nuclear accident emergency agencies attach high importance is that lost radioactive sources are searched quickly, panic of people is relieved, and harm of nuclear radiation to the public is reduced. In the searching process of the radioactive source, various factors restrict the use of a vehicle-mounted or airborne nuclear radiation monitoring technology; the monitoring of the nuclear radiation on foot can adapt to various conditions and environments, and is an important means for searching radioactive sources.
In practice, the principle and method for searching for a lost radioactive source by using a nuclear radiation monitor are that when a real radioactive source is placed at a point M, a measurer at the point N holds the nuclear radiation monitor to move forward towards the point M for measurement, the nuclear radiation dose rate displayed on the monitor is gradually increased along with the gradual approach of the measurer to the point M, and when the maximum value measurable by the scene is reached, the position of the radioactive source is the position of the nuclear radiation monitor. The principle and the method are utilized to carry out teaching training on the emergency rescue personnel of the nuclear accident, so that the personnel can know the nuclear accident, know the radioactive source and master the means and the method for measuring the nuclear radiation in the usual teaching training, and the capability of the emergency rescue personnel for searching the radioactive source can be effectively improved.
At present, under the condition of practical teaching and training, a real radioactive source or an electromagnetic radiation source (one type of simulated radioactive source) is generally adopted together with a radiation monitor to carry out radioactive source searching and training on nuclear accident emergency rescue personnel. In the face of a real radioactive source, teaching personnel usually have fear and are unwilling to contact or approach to measurement, and the teaching training is directly influenced; the harm of the electromagnetic radiation source used as a simulated radiation source is far less than that of a real radiation source, but the maintenance and use cost of electromagnetic wave emission equipment is higher, and the electromagnetic radiation also has certain harm to human bodies and does not belong to a completely harmless simulated radiation source.
Disclosure of Invention
The invention aims to provide a completely harmless gamma radioactive source simulation searching training system and provides a gamma radioactive source simulation searching method based on the system so as to meet the teaching training requirements of nuclear accident emergency rescue and radioactive source searching in the field or nuclear radiation monitoring.
In order to achieve the aim, the invention provides a simulated gamma radioactive source searching and training system which is characterized by comprising a simulated nuclear radiation monitor, a simulated gamma radioactive source and a simulated radioactive source parameter setting device, wherein the simulated nuclear radiation monitor comprises a microcomputer I (1), a global positioning module I (2), an alarm display module (3), a power supply module I (4) and a wireless communication interface I (5), the simulated gamma radioactive source comprises a microcomputer II (6), a global positioning module II (7), a power supply module II (8) and a wireless communication interface II (9), the simulated radioactive source parameter setting device comprises a simulated radioactive source parameter setting module (10), a power supply module III (11) and a wireless communication interface III (12), the global positioning module I (2) provides the position information of the simulated nuclear radiation monitor, the second global positioning module (6) provides position information of a simulated gamma radiation source, the first wireless communication interface (5) and the second wireless communication interface (9) transmit signals in a wireless mode, and the second wireless communication interface (9) and the third wireless communication interface (12) transmit signals in a wireless mode.
In the above technical solution, the first global positioning module (2) and the second global positioning module (6) are beidou global positioning modules or GPS global positioning modules.
In order to achieve the above object, the present invention further provides a method for searching a simulated gamma radiation source, which is characterized in that:
firstly, a searching system comprising a simulated nuclear radiation monitor, a simulated gamma radiation source and a simulated radiation source parameter setting device is constructed, wherein the simulated nuclear radiation monitor comprises a microcomputer I (1), a global positioning module I (2), an alarm display module (3), a power supply module I (4) and a wireless communication interface I (5), the simulated gamma radiation source comprises a microcomputer II (6), a global positioning module II (7), a power supply module II (8) and a wireless communication interface II (9), the simulated radiation source parameter setting device comprises a simulated radiation source parameter setting module (10), a power supply module III (11) and a wireless communication interface III (12), the global positioning module I (2) provides position information of the simulated nuclear radiation monitor, the global positioning module II (6) provides position information of the simulated gamma radiation source, the wireless communication interface I (5) and the wireless communication interface II (9) transmit signals in a wireless mode, and the wireless communication interface II (9) and the wireless communication interface III (12) transmit signals in a wireless mode;
and secondly, acquiring the distance x (m) between the simulated nuclear radiation monitor and the simulated gamma radioactive source according to the positioning information respectively provided by the simulated nuclear radiation monitor and the simulated gamma radioactive source. The nuclear radiation dose value generated by a known gamma radioactive source point source (when the measuring distance is more than 10 times of the diameter of the radioactive source, the radioactive source can be regarded as the point source) at a certain distance is influenced by two factors, one is that the gamma rays emitted by the gamma radioactive source point source generate dose rate at any peripheral distance which is inversely proportional to the square of the distance, namely, the distance square inverse proportion law is obeyed, and the other is that the gamma rays can react with air molecules to attenuate when passing through the air, and the dose rate obeys the exponential attenuation law, as shown in the formula (I),
In the formula:
Rxdose rate at x meters from the source (Gy/h);
a-activity of radioactive source (Bq);
gamma-air kerma rate constant (Gy. m)2.Bq-1.S-1) The nuclide can be obtained by looking up a table after being determined;
mu-linear attenuation coefficient (cm) of shielding material (e.g. air)-1) The coefficient is related to the type of the shielding material and the ray energy generated by the radioactive source and can be obtained by looking up a table;
x is the distance (m) from the measuring point to the radioactive source, and the calculation formula (II) is as follows,
In the formula:
x is the distance (m) from the simulated nuclear radiation monitor to the simulated radiation source;
r-mean radius of the earth, equal to 6.371X 106m；
Phi 1 represents the latitude of the position where the simulated nuclear radiation monitor is located;
λ 1-the longitude of the position where the simulated nuclear radiation monitor is located;
After the nuclide and the radioactivity A of the simulated gamma radioactive source are determined, calculating the simulated dose rate (Gy/h) at a position x meters away from the simulated gamma radioactive source according to the air kerma rate constant gamma, the linear attenuation coefficient mu of the air and the distance x between a measuring point and the radioactive source;
thirdly, utilizing the data acquisition, storage and calculation functions of the microcomputer I (1) in the simulated nuclear radiation monitor, the related parameters and formulas required for calculating the simulated dose rate by using the formula I, such as the air specific kinetic energy constant gamma and the linear attenuation coefficient mu of the air of dozens of gamma radioactive nuclides, the calculation formula of the distance x from the measuring point to the radioactive source and the dose rate RxThe calculation formulas are stored in a first microcomputer (1) of the simulated nuclear radiation monitor, and the first microcomputer (1) acquires, calls and calculates data once to obtain R with different valuesxAnd finally finding a simulated gamma radioactive source.
In the above method for searching a simulated gamma radioactive source, the nuclides of the simulated gamma radioactive source include several dozens of radionuclides common in nuclear accidents, such as cobalt-60, cesium-137, and iodine-131.
In the above method for searching a simulated gamma radiation source, the value of the activity a can be set to any positive number, and the unit is Bq.
In the above method for searching a simulated gamma radiation source, the specific steps are as follows:
s1, storing the air kerma constant gamma of radioactive nuclide, the line attenuation coefficient mu of air and the average radius r of the earth in a microcomputer I (1) of the analog nuclear radiation monitor in advance;
s2, setting a simulated gamma radiation source, presetting a nuclide name and a radioactivity value in a simulated radiation source parameter setting module (10) as initial parameters of the simulated gamma radiation source, sending the initial parameters to a wireless communication interface II (9) through a wireless communication interface III (12), and then transmitting the initial parameters to a simulated gamma radiation source microcomputer II (6) for storage;
s3, sending an inquiry signal to a second wireless communication interface (9) of the simulated gamma radiation source through a first wireless communication interface (5) by a first microcomputer (1) of the simulated nuclear radiation monitor, reading the positioning information of a second global positioning module (7) and the nuclide name and radioactivity information of the simulated gamma radiation source preset in the second microcomputer (6) after the second microcomputer (6) of the simulated gamma radiation monitor receives the inquiry information of the first microcomputer (1) of the simulated nuclear radiation monitor, sending the information to the first wireless communication interface (5) through the second wireless communication interface (9), and storing the information into the first microcomputer (1) of the simulated nuclear radiation monitor;
s4, reading longitudes phi 1 and phi 2 and latitudes lambda 1 and lambda 2 of a global positioning module I (2) and a global positioning module II (7) and reading the average radius r of the earth in a memory by a microcomputer I (1), substituting the read longitudes phi 1 and phi 2 and latitudes lambda 1 and lambda 2 into a software calculation program written according to a formula II, calculating to obtain the distance x between the simulated nuclear radiation monitor and the simulated gamma radiation source, and storing the distance x into a specified storage unit in the microcomputer I (1);
s5, the microcomputer I (1) of the simulated nuclear radiation monitor reads the stored nuclide name of the simulated gamma radioactive source to call the radioactivity value A, the air kerma rate constant gamma, the air line attenuation coefficient mu and the distance value x between the simulated gamma radioactive source and the simulated nuclear radiation monitor, and substitutes the values into the software calculation program written according to the formula I to calculate and obtain the dose rate value R at the measuring pointx；
S6, measuring the dosage rate value R at the pointxSending an alarm display module (3) of the simulation nuclear radiation monitor to display (Gy/h or mGy/h or mu Gy/h), and giving sound-light alarm if the alarm threshold value is exceeded;
s7, repeating the above steps S4 to S6, when the distance x between the measuring point and the simulated gamma radioactive source is changed, calculating the dose rate value R at the new measuring pointxWith dose rate value R at the new measurement pointxThe distance between the new measuring point and the simulated gamma radioactive source is gradually reduced once by increasing once, and the search of the simulated gamma radioactive source is further completed.
In the step S1 of the above method for searching a simulated gamma radiation source, the method for obtaining the air kerma rate constant Γ of each radionuclide pre-stored in the first microcomputer (1) of the simulated nuclear radiation monitor is as follows: the air kerma rate constant gamma of each radionuclide is searched manually from the related manual, then the air kerma rate constant gamma of each radionuclide is input into the corresponding storage area of the microcomputer I (1) to be stored permanently, each gamma has a unique storage address in the memory, when the dose rate is calculated, the microcomputer I (1) determines the storage address of the gamma according to the name of the nuclide, and the gamma is called from the memory by using the address.
In the step S1 of the above method for searching a simulated γ -ray source, the method for obtaining the attenuation coefficient μ of each radionuclide air line pre-stored in the microcomputer i (1) is as follows: manually finding out the mass attenuation coefficient mu/rho (rho is the air density) of gamma rays with various energies in the air from a related manual, calculating to obtain the mu/rho value corresponding to the energy of each radionuclide by adopting a linear interpolation method because the energy corresponding to the mass attenuation coefficient mu/rho value given by the manual cannot correspond to the energy of most common radionuclides, and multiplying the mu/rho value corresponding to the energy of each radionuclide by rho =0.001293g/cm3The method comprises the steps of (air density) obtaining mu values, inputting the calculated linear attenuation coefficient mu of various common radionuclides in the air into a corresponding storage area in a microcomputer I (1) in a manual mode for permanent storage, wherein each mu value has a unique storage address in a memory, and when the dose rate is calculated, the microcomputer I (1) determines the storage address of the mu value according to the nuclide name and uses the address to call the mu value from the memory.
The invention has the advantages that the simulated gamma radioactive source (hereinafter referred to as a simulated source), the simulated radioactive source parameter setting device and the simulated nuclear radiation monitor (hereinafter referred to as a simulated radiation instrument) are organically combined, the simulated radioactive source is finally found by calculating the simulated radiation intensity (namely the simulated dose rate) generated by the simulated rays emitted by the simulated radioactive source at the measuring point, although the actual measurement is replaced by the calculation result, the measuring method is the same as the display mode, the difference between the two cannot be sensed by a measuring person, and the scene which is infinitely close to the real radiation source searching is presented to the measuring person. In order to obtain better teaching and training effects, the simulated radiometer has the advantages that the appearance size, the weight, the color, the measurement and sampling time length, the displayed numerical unit, the over-threshold alarm and the operation method are completely the same as those of the nuclear radiation monitor used in teaching and training, but the internal structure is different.
The invention can complete the simulation training of different types and different activities of the lost gamma radioactive sources in the actual environment in the field, approaches the actual scene of the radioactive sources infinitely, has wide searching range, is not influenced by climate and obstacles, and has simple and effective means and method. The harmless simulation source does not cause harm to human bodies.
The invention meets the teaching and training requirements of emergency rescue of nuclear accidents and radioactive source searching.
Drawings
FIG. 1 is a schematic diagram of a system for training a search of a simulated gamma radiation source according to the present invention.
Fig. 2 is a schematic configuration diagram of a first embodiment of the present invention.
In the above drawings, 1 is a first microcomputer, 2 is a first global positioning module, 3 is an alarm display module, 4 is a first power supply module, 5 is a first wireless communication interface, 6 is a second microcomputer, 7 is a second global positioning module, 8 is a second power supply module, 9 is a second wireless communication interface, 10 is a simulated radiation source parameter setting module, 11 is a third power supply module, 12 is a third wireless communication interface, 101 is a first microcomputer, 102 is a first global positioning module, 103 is an alarm display module, 104 is a first power supply module, 105 is a first wireless communication interface, 106 is a second microcomputer, 107 is a second global positioning module, 108 is a second power supply module, 109 is a second wireless communication interface, 110 is a simulated radiation source parameter setting module, 111 is a third power supply module, and 112 is a third wireless communication interface.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
The present embodiment provides a simulated radiation source search training system, which is configured as shown in fig. 2. The simulated radiation instrument comprises a first microcomputer 101, a first global positioning module 102, an alarm display module 103, a first power supply module 104 and a first wireless communication interface 105, the simulated source comprises a second microcomputer 106, a second global positioning module 107, a second power supply module 108 and a second wireless communication interface 109, and the simulated radiation source parameter setting device comprises a simulated radiation source parameter setting module 110, a third power supply module 111 and a third wireless communication interface 112.
The first power supply module 104 provides power for the first microcomputer 101, the first global positioning module 102, the display alarm module 103 and the first wireless communication interface 105, so that long-term operation of the mobile terminal is ensured. The second power module 108 provides power to the second microcomputer 106, the second global positioning module 107 and the second wireless communication interface 109 to ensure long-term operation thereof. The third power module 111 provides power for the simulated radiation source setting module 110 and the third wireless communication interface 112 to ensure long-term operation thereof.
The first global positioning module 102 provides position information for the analog radiometer. The second global positioning module 107 provides position information for the analog source. The only use of the two position information is for calculating the distance between the analog radiometer and the analog source.
The first wireless communication interface 105 and the second wireless communication interface 109 transmit signals in a wireless mode; the second wireless communication interface 109 and the third wireless communication interface 112 transmit signals in a wireless manner.
The steps of the analog source searching method of this embodiment are as follows,
the first step is to store the air kerma constant gamma, the air line attenuation coefficient mu and the earth average radius r of the radioactive nuclide in the microcomputer 101 of the analog nuclear radiation monitor in advance.
In the first step, the method for obtaining the air kerma rate constant Γ of each radionuclide pre-stored in the first microcomputer 101 of the simulated nuclear radiation monitor is as follows: first, the air kerma constant Γ of each radionuclide is manually found from the related manual. Such as cobalt-60, with a kinetic rate constant of beta =8.67 × 10-17（Gy.m2.Bq-1.s-1) Cesium-137, its Γ =2.12 × 10-17（Gy.m2.Bq-1.s-1) Iodine-131, its Γ =1.44 × 10-17（Gy.m2.Bq-1.s-1) Etc. and secondly, releasing the air ratio of each radionuclideThe kinetic energy constant gamma is input into the corresponding memory area of the microcomputer 101 for permanent storage, each gamma has a unique memory address in the memory, when the dosage rate is calculated, the microcomputer 101 determines the memory address of the gamma according to the name of the nuclide, and the gamma is called from the memory by using the address.
In the first step, the method for obtaining the attenuation coefficient μ of the air line of each radionuclide stored in the first microcomputer 101 in advance comprises the following steps: firstly, manually finding out the mass attenuation coefficient mu/rho (rho is the air density) of gamma rays with various energies in the air from a related manual; secondly, because the energy corresponding to the mass attenuation coefficient mu/rho value given by the manual cannot correspond to the energy of most common radionuclides, the mu/rho value corresponding to the energy of each radionuclide is calculated by adopting a linear interpolation method. As given in the manual, the value of the [ mu ]/rho of a certain gamma ray with the energy of 0.6MeV is 0.0804 (cm)2G), a value of 0.0706 (cm) for [ mu ]/rho of a certain gamma ray with an energy of 0.8MeV2In the case of the cesium-137 nuclide,/g), the μ/ρ of the nuclide having a radiation energy greater than 0.6MeV and less than 0.8MeV is not given, and the μ/ρ of the nuclide having a radiation energy of 0.662MeV cannot be found, and the value is 0.0774 only by calculation using linear interpolation; secondly, multiplying the mu/rho value corresponding to each radionuclide energy by rho =0.001293g/cm3Obtaining a mu value (air density); finally, the calculated line attenuation coefficient mu of various common radionuclides in the air is manually input into a corresponding storage area in the first microcomputer 101 to be permanently stored, each mu value has a unique storage address in the memory, and when the dose rate is calculated, the first microcomputer 101 determines the storage address of the mu value according to the nuclide name and uses the address to call the mu value from the memory.
Setting a simulated gamma radiation source, presetting a nuclide name and a radioactivity value as initial parameters of the simulated gamma radiation source in a simulated radiation source parameter setting module 10, sending the initial parameters to a second wireless communication interface 109 through a third wireless communication interface 112, and then transmitting the initial parameters to a second simulated gamma radiation source microcomputer 106 for storage.
In the second step, the nuclides simulating the gamma radioactive source comprise dozens of common radionuclides in nuclear accidents, such as cobalt-60, cesium-137, iodine-131 and the like.
In the second step, the radioactivity A value can be set to any positive number in Bq.
And step three, the first microcomputer 101 of the simulated nuclear radiation monitor sends an inquiry signal to the second wireless communication interface 109 of the simulated gamma radiation source through the first wireless communication interface 105, and after receiving inquiry information of the first microcomputer 101 of the simulated nuclear radiation monitor, the second microcomputer 106 of the simulated gamma radiation source reads positioning information of the second global positioning module 107 and nuclide name and radioactivity information of the simulated gamma radiation source preset in the second microcomputer 106, sends the nuclide name and radioactivity information to the first wireless communication interface 105 through the second wireless communication interface 109, and stores the nuclide name and radioactivity information into the first microcomputer 101 of the simulated nuclear radiation monitor.
And fourthly, the first microcomputer 101 reads longitudes Φ 1 and Φ 2 and latitudes λ 1 and λ 2 where the first global positioning module 102 and the second global positioning module 107 are located, reads the average radius r of the earth in the memory, substitutes the average radius r into a software calculation program written according to the formula (II), calculates and obtains the distance x between the simulated nuclear radiation monitor and the simulated gamma radiation source, and stores the distance x into a specified storage unit in the first microcomputer 101.
Step five, the microcomputer I101 of the simulation nuclear radiation monitor calls a radioactivity activity value A, an air kerma kinetic energy rate constant gamma, an air line attenuation coefficient mu and a distance value x between the simulation gamma radiation source and the simulation nuclear radiation monitor according to the stored nuclide name of the simulation gamma radiation source, and substitutes the values into a software calculation program written according to the formula I to calculate and obtain a dose rate value R at a measuring pointx。
Step six, measuring the dose rate value R at the measuring pointxAnd an alarm display module 103 of the simulation nuclear radiation monitor is sent to display (Gy/h or mGy/h or mu Gy/h), and if the alarm threshold value is exceeded, an audible and visual alarm is given.
Step seven, repeating the steps four to six, when the measuring point and the simulated gamma radiation source are in contactThe distance x is changed, and the dose rate value R at the new measuring point is calculatedxWith dose rate value R at the new measurement pointxThe distance between the new measuring point and the simulated gamma radioactive source is gradually reduced once by increasing once, and the search of the simulated gamma radioactive source is further completed.
In actual radiation source searching scenes, for example, searching scattered nuclear material fragments (radiation sources) or searching hidden radiation sources, the number of the radiation sources may be one or more, and multiple persons need to hold one nuclear radiation monitor for simultaneous searching. Therefore, in order to approach the scene of the actual search radiation source, one or more simulation sources may be set during training and may be distributed in a single point or multiple points. In order to obtain a better teaching and training effect, the simulated radiometer in the embodiment has the same overall dimension, weight, color, measurement and sampling time length, displayed numerical units, over-threshold alarm and operation method as those of the nuclear radiation monitor used in teaching and training. When the searching person holds one analog radiometer to search the analog source in carpet form, several persons may find the same analog source at the same time, or may find different analog sources. In the process of searching for the simulated source, because the indexes of the simulated radiation instrument are completely the same as those of the nuclear radiation monitor used in teaching training, operators cannot perceive the difference between the simulated radiation instrument and the nuclear radiation monitor, and the operator is presented with a scene which is infinitely close to reality and searches for nuclear material fragments or radioactive sources.
Claims (8)
1. A simulated gamma radiation source searching and training system is characterized by comprising a simulated nuclear radiation monitor, a simulated gamma radiation source and a simulated radiation source parameter setting device, wherein the simulated nuclear radiation monitor comprises a microcomputer I (1), a global positioning module I (2), an alarm display module (3), a power supply module I (4) and a wireless communication interface I (5), the simulated gamma radiation source comprises a microcomputer II (6), a global positioning module II (7), a power supply module II (8) and a wireless communication interface II (9), the simulated radiation source parameter setting device comprises a simulated radiation source parameter setting module (10), a power supply module III (11) and a wireless communication interface III (12), the global positioning module I (2) provides position information of the simulated nuclear radiation monitor, the global positioning module II (6) provides position information of the simulated gamma radiation source, the first wireless communication interface (5) and the second wireless communication interface (9) transmit signals in a wireless mode, and the second wireless communication interface (9) and the third wireless communication interface (12) transmit signals in a wireless mode.
2. The simulated gamma radiation source search training system of claim 1, wherein: the first global positioning module (2) and the second global positioning module (6) are Beidou global positioning modules or GPS global positioning modules.
3. A method for searching a simulated gamma radiation source is characterized in that:
firstly, a searching system comprising a simulated nuclear radiation monitor, a simulated gamma radiation source and a simulated radiation source parameter setting device is constructed, wherein the simulated nuclear radiation monitor comprises a microcomputer I (1), a global positioning module I (2), an alarm display module (3), a power supply module I (4) and a wireless communication interface I (5), the simulated gamma radiation source comprises a microcomputer II (6), a global positioning module II (7), a power supply module II (8) and a wireless communication interface II (9), the simulated radiation source parameter setting device comprises a simulated radiation source parameter setting module (10), a power supply module III (11) and a wireless communication interface III (12), the global positioning module I (2) provides position information of the simulated nuclear radiation monitor, the global positioning module II (6) provides position information of the simulated gamma radiation source, the wireless communication interface I (5) and the wireless communication interface II (9) transmit signals in a wireless mode, and the wireless communication interface II (9) and the wireless communication interface III (12) transmit signals in a wireless mode;
secondly, calculating and obtaining the distance x (m) between the simulated nuclear radiation monitor and the simulated gamma radiation source according to the positioning information respectively provided by the simulated nuclear radiation monitor and the simulated gamma radiation source, wherein the nuclear radiation dose value generated by a known gamma radiation source point source (the radiation source can be regarded as the point source when the measured distance is more than 10 times of the diameter of the radiation source) at a certain distance is influenced by two factors, one factor is that the gamma ray emitted by the gamma radiation source point source generates dose rate which is inversely proportional to the square of the distance at any distance on the periphery, namely, the distance square inverse proportion law is obeyed, the other factor is that the gamma ray can act on air molecules to be attenuated when passing through the air, the dose rate obeys the exponential attenuation law as shown in the formula (I),
In the formula:
Rxdose rate at x meters from the source (Gy/h);
a-activity of radioactive source (Bq);
gamma-air kerma rate constant (Gy. m)2.Bq-1.S-1) The nuclide can be obtained by looking up a table after being determined;
mu-linear attenuation coefficient (cm) of shielding material (e.g. air)-1) The coefficient is related to the type of the shielding material and the ray energy generated by the radioactive source and can be obtained by looking up a table;
x is the distance (m) from the measuring point to the radioactive source, and the calculation formula (II) is as follows,
In the formula:
x is the distance (m) from the simulated nuclear radiation monitor to the simulated radiation source;
r-mean radius of the earth, equal to 6.371X 106m；
Phi 1 represents the latitude of the position where the simulated nuclear radiation monitor is located;
phi 2 is the latitude of the position of the simulated radioactive source;
λ 1-the longitude of the position where the simulated nuclear radiation monitor is located;
λ 2 — the longitude of the position where the simulated radiation source is located;
after the nuclide and the radioactivity A of the simulated gamma radioactive source are determined, calculating the simulated dose rate (Gy/h) at a position x meters away from the simulated gamma radioactive source according to the air kerma rate constant gamma, the linear attenuation coefficient mu of the air and the distance x between a measuring point and the radioactive source;
thirdly, utilizing the data acquisition, storage and calculation functions of the microcomputer I (1) in the simulated nuclear radiation monitor, the related parameters and formulas required for calculating the simulated dose rate by using the formula I, such as the air specific kinetic energy constant gamma and the linear attenuation coefficient mu of the air of dozens of gamma radioactive nuclides, the calculation formula of the distance x from the measuring point to the radioactive source and the dose rate RxThe calculation formulas are stored in a first microcomputer (1) of the simulated nuclear radiation monitor, and the first microcomputer (1) acquires, calls and calculates data once to obtain R with different valuesxAnd finally finding a simulated gamma radioactive source.
4. A method as claimed in claim 3, wherein the method comprises: the nuclide of the simulated gamma radioactive source comprises common radionuclides in dozens of nuclear accidents such as cobalt-60, cesium-137, iodine-131 and the like.
5. A method as claimed in claim 3, wherein the method comprises: the radioactivity A value can be set to any positive number in Bq.
6. A method as claimed in claim 3, wherein the method comprises: the method for simulating the search of the gamma radiation source comprises the following specific steps,
s1, storing the air kerma rate constant gamma, the air line attenuation coefficient mu and the earth average radius r of dozens of common radionuclides in a microcomputer I (1) of the analog nuclear radiation monitor in advance;
s2, setting a simulated gamma radiation source, presetting a nuclide name and a radioactivity value in a simulated radiation source parameter setting module (10) as initial parameters of the simulated gamma radiation source, sending the initial parameters to a wireless communication interface II (9) through a wireless communication interface III (12), and then transmitting the initial parameters to a simulated gamma radiation source microcomputer II (6) for storage;
s3, sending an inquiry signal to a second wireless communication interface (9) of the simulated gamma radiation source through a first wireless communication interface (5) by a first microcomputer (1) of the simulated nuclear radiation monitor, reading the positioning information of a second global positioning module (7) and the nuclide name and radioactivity information of the simulated gamma radiation source preset in the second microcomputer (6) after the second microcomputer (6) of the simulated gamma radiation monitor receives the inquiry information of the first microcomputer (1) of the simulated nuclear radiation monitor, sending the information to the first wireless communication interface (5) through the second wireless communication interface (9), and storing the information into the first microcomputer (1) of the simulated nuclear radiation monitor;
s4, reading longitudes phi 1 and phi 2 and latitudes lambda 1 and lambda 2 of a global positioning module I (2) and a global positioning module II (7) and reading the average radius r of the earth in a memory by a microcomputer I (1), substituting the read longitudes phi 1 and phi 2 and latitudes lambda 1 and lambda 2 into a software calculation program written according to a formula II, calculating to obtain the distance x between the simulated nuclear radiation monitor and the simulated gamma radiation source, and storing the distance x into a specified storage unit in the microcomputer I (1);
s5, the microcomputer I (1) of the simulation nuclear radiation monitor calls a radioactivity activity value A, an air kerma rate constant line gamma, an air line attenuation coefficient mu and a distance value x between the simulation gamma radiation source and the simulation nuclear radiation monitor according to the stored nuclide name of the simulation gamma radiation source, and substitutes the invoked radioactivity activity value A, the air kerma rate constant line gamma, the air line attenuation coefficient mu and the distance value x between the simulation gamma radiation source and the simulation nuclear radiation monitor into a software calculation program written according to the formula I to calculate and obtain a dose rate value R at a measuring pointx；
S6, measuring the dosage rate value R at the pointxSending an alarm display module (3) of the simulation nuclear radiation monitor to display (Gy/h or mGy/h or mu Gy/h), and giving sound-light alarm if the alarm threshold value is exceeded;
s7, repeating the above steps S4 to S6, when the distance x between the measuring point and the simulated gamma radioactive source is changed, calculating the dose rate value R at the new measuring pointxWith new measuring pointsTreatment of dose rate value RxThe distance between the new measuring point and the simulated gamma radioactive source is gradually reduced once by increasing once, and the search of the simulated gamma radioactive source is further completed.
7. The method of claim 6, wherein: in the step S1, the method for obtaining the air kerma rate constant Γ of each radionuclide stored in the microcomputer i (1) of the simulated nuclear radiation monitor in advance includes manually searching the air kerma rate constant Γ of each radionuclide from a related manual, inputting the air kerma rate constant Γ of each radionuclide into a corresponding storage area of the microcomputer i (1) for permanent storage, wherein each Γ value has a unique storage address in a memory, and when calculating the dose rate, the microcomputer i (1) determines the storage address of the Γ value according to the name of the nuclide, and uses the address to retrieve the Γ value from the memory.
8. The method of claim 6, wherein: in the step S1, the method for obtaining the air line attenuation coefficient μ of each radionuclide stored in the microcomputer i (1) in advance includes manually finding out the mass attenuation coefficient μ/ρ (ρ is the air density) of the γ -ray of each energy in the air from the manual, calculating the μ/ρ value corresponding to each radionuclide energy by linear interpolation since the energy corresponding to the mass attenuation coefficient μ/ρ value given by the manual does not correspond to the energy of most common radionuclides, and multiplying the μ/ρ value corresponding to each radionuclide energy by ρ =0.001293g/cm3Obtaining mu value (air density), inputting the calculated linear attenuation coefficient mu of various common radioactive nuclides in the air into a corresponding storage area in a microcomputer I (1) in a manual mode for permanent storage, wherein each mu value has a unique storage address in a memory, and when calculating the dose rate, the microcomputer I (1) determines the storage address of the mu value according to the nuclide name and uses the address to obtain the radiation attenuation coefficient mu of various common radioactive nuclides in the airThe μ value is recalled from memory.
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