WO2019109813A1 - Method for measuring neutron dose rate by means of cerium bromide detector, and neutron dose rate meter - Google Patents

Abstract

A method for measuring a neutron dose rate by means of a cerium bromide detector, and a neutron dose rate meter. The method for measuring a neutron dose rate uses a deterministic function relationship between net count rates of neutron characteristic γ energy peaks produced by neutrons in the cerium bromide detector and neutron dose rates created by the neutrons at the points, and calculates a neutron dose rate by measuring a γ energy spectrum and using the deterministic function relationship.

Description

Method for measuring neutron dose rate using cesium bromide detector and neutron dose rate meter Technical field

The present disclosure relates to the field of radiation detection, environmental monitoring equipment, and in particular, the present disclosure relates to a method for measuring a neutron dose rate using a cesium bromide detector and a neutron dose rate meter.

Background technique

The neutron dose rate meter is a radiation monitoring device for measuring and evaluating the surrounding dose equivalent rate produced by neutron radiation. At present, the common neutron dose rate meter for radiation protection consists of a slower body, a neutron energy compensation material, a thermal neutron sensitive counter, and an electronic circuit. The structural feature is that the thermal neutron sensitive counter is wrapped around the center with a spherical or cylindrical slowing body; in the slowing body, a neutron absorption screen with a slow neutron permeation hole is arranged at a certain distance from the central detector. Or with an absorbing layer containing a boron-containing material, the incident neutron is slowed down (or thermally neutron-diffused) after being incident on the moderator, and a part of the slow (thermal) neutron is absorbed when passing through the absorption sieve (or absorption layer), necessarily The proportion of neutrons passes through, and the neutrons that pass through the absorption screen continue to be slowed or diffused, and finally some of the neutrons that reach the central detector are detected and recorded.

The existing neutron dose rate meter can be roughly divided into three categories according to the structural design: one is a single counter type, and the dose rate meter adopts a single spherical or cylindrical polyethylene as a slowing body, and the center of the sphere is placed in a single body. Proportional counters (such as BF ₃ , ³ He) or ⁶ Li glass scintillators, with some specially designed neutron energy compensation materials such as boron plastic or cadmium materials. The second is the multi-counter type. The slower body of this type of dose rate meter is designed with single or multi-ball. The probe adopts multiple proportional counters (such as ³ He), which are placed on the center of the slowing body or the spherical surface. Neutron energy compensation material. The third is the spectrometer type. These dose rate meters enclose the thermal neutron detectors in the slow-reducing spherical shells of different diameters. The slowing ability of different size slowing balls is different, and the neutron response of different energies is obtained. The measured slowed neutron energy spectrum is despread, the actual energy spectrum of the neutron radiation field is solved, and the neutron dose rate of the radiation field is calculated.

The ruthenium bromide detector is another new type of inorganic scintillation detector discovered after the cesium bromide detector, which has good time resolution (hundreds of picoseconds) and high energy resolution (<4%, for 662keV gamma ray), high detection efficiency and low intrinsic background can be applied to gamma spectroscopy. As an inorganic scintillator detector, the cesium bromide detector is mainly composed of strontium bromide crystal. The constituent elements mainly include Ce and Br. Considering the abundance of natural isotopes, mainly ¹⁴⁰ Ce, ⁷⁹ Br and ⁸¹ Br, three nuclides Both are stable nuclides. However, when a neutron is incident on a cesium bromide crystal material, the neutron reacts with the target species nuclides. The main types of reactions include elastic scattering, inelastic scattering, and radiation trapping. Wherein, if the neutron kinetic energy is sufficient to excite the target nucleus and the inelastic scattering A(n,n'γ)A' occurs, the incident neutron will transfer a part of the initial kinetic energy to the nucleus, causing the target nucleus to excite to the excited state, and the target nucleus When de-excited, gamma rays are emitted, for example, ⁷⁹ Br(n, n'γ) ^79m Br, ^79m Br de-excitation emits γ-ray energy of 217keV; if radiation capture reaction A(n, γ)B occurs, target-nuclear capture The neutron produces a new target nucleus. The new nucleus is usually in an unstable excited state. The excitation energy depends on the binding energy and kinetic energy of the neutron. The excited nucleus will jump back to the ground state by emitting one or several gamma quantums. transmitting subsequent radioactive decay, for example, ^{140 Ce (n, γ) 141} Ce, 141 Ce to β ^- form of the decay of ^{141 Pr; 79 Br (n,} γ) 80 Br, 80 Br to β ^- and orbital electron capture manner Decay to ⁸⁰ Kr; ⁸¹ Br(n, γ) ⁸² Br, ⁸² Br decays to ⁸² Kr in a β ^- form. The gamma rays of different energies produced by the nuclear reaction can be detected and resolved by the cesium bromide detector.

In recent years, with the deepening of research, foreign researchers have found through experiments that using the above-mentioned nuclear reaction to generate gamma-ray physical mechanism, using the time-of-flight method, the detection of neutrons by the cesium bromide detector can be realized. However, the above detection method is based on the time-of-flight method and is not suitable for the field of radiation protection: since the time-of-flight method is based on the difference in the time required for a neutron to fly over a certain distance based on different energy (flight speed), the measurement of the neutron energy will be performed. Converting to the measurement of the time required to fly the neutron over the selected distance, by measuring the time distribution to determine the neutron energy distribution, the method requires extremely accurate recording of the starting and ending moments of the neutron over the flight distance, which is The field of radiation protection is clearly unachievable.

Therefore, the present disclosure proposes a neutron dose rate meter based on a cesium bromide detector to measure the neutron dose rate of the radiation field by measuring the net count rate and the spectrum of the characteristic gamma peak of the neutron.

Public content

The present disclosure aims to solve at least one of the technical problems in the related art to some extent. To this end, an object of the present disclosure is to provide a method for measuring a neutron dose rate and a neutron dose rate meter, using the method for measuring a neutron dose rate proposed by the present disclosure, which can utilize a cesium bromide detector to interact with an incident neutron The reaction occurs, producing characteristic gamma peaks of different energies, and detecting and resolving using a cesium bromide detector, thereby obtaining a neutron using a deterministic functional relationship between the neutron dose rate and the net count rate of the characteristic gamma peaks. Dose rate.

The inventors found that the detection of neutrons by the cesium bromide detector can be achieved by the time-of-flight method, but the neutron energy distribution is determined in the field of radiation protection by accurately recording the start and end times of the neutrons at the selected flight distance. Unachievable, the time-of-flight method does not apply to the field of radiation protection. The inventors have unexpectedly discovered that the change in the net count (net count rate) of the characteristic gamma energy peaks of different energies produced by the reaction of neutrons with strontium bromide crystal materials is consistent with the trend of neutron dose rate, using neutron doses. The deterministic functional relationship between the rate and the net count of the characteristic gamma energy peak (net count rate) can be achieved by measuring the net count (net count rate) combination of one or several neutron features γ energy peaks and the solution calculation. Measurement of the neutron dose rate in the radiation field.

To this end, in accordance with a first aspect of the present disclosure, the present disclosure provides a method of measuring a neutron dose rate, wherein the method utilizes neutrons generated in a ruthenium bromide detector, in accordance with a particular embodiment of the present disclosure There is a deterministic functional relationship between the net count rate of the sub-featured gamma energy peaks and the neutron dose rate caused by the neutrons at that point, by measuring the gamma energy spectrum and using the deterministic functional relationship to calculate The neutron dose rate was obtained.

The method for measuring the neutron dose rate according to the present disclosure is actually based on the discovery by the inventors that the net count rate of the neutron characteristic gamma energy peak generated by the neutron in the cesium bromide detector is the same as the neutron There is a deterministic functional relationship between the neutron dose rates caused by the points. In turn, a neutron dose rate meter based on a cesium bromide detector can be used to measure the characteristic gamma peak combination produced by one or several incident neutrons, and between the neutron dose rate and the net count rate of the neutron characteristic gamma peak. A deterministic functional relationship yields a neutron dose rate.

In some embodiments of the present disclosure, the method of measuring a neutron dose rate comprises:

The neutron is detected by a cesium bromide detector to obtain a characteristic gamma peak;

Calculating a neutron dose rate based on the characteristic gamma energy peak, wherein the neutron dose rate is a deterministic functional relationship with the net gamma energy peak of the characteristic gamma energy peak, and the functional relationship can be expressed as:

D _i =f(N _i )

Wherein, D _i is the neutron dose rate, and the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps.

In some embodiments of the present disclosure, in the deterministic functional relationship, the net count rate ranges from: N _i >0.

In some embodiments of the present disclosure, in the deterministic functional relationship, the neutron dose rate is measured in a range of: D _i >0.

In some embodiments of the present disclosure, the neutron is generated by a source of germanium. Thereby, neutrons of different energies can be generated and reacted with strontium bromide crystals to generate characteristic gamma peaks of different energies, which can be obtained by using a functional relationship between the neutron dose rate and the net count rate of the peak positions. Neutron dose rate.

In some embodiments of the present disclosure, the characteristic gamma energy peak comprises at least one selected from the group consisting of: 557.76±5 keV, 83.93±5 keV, 101.8±5 keV, 121.1±5 keV, 174.8±10 keV, 207.9±5 keV 215.6±10 keV, 245.1±10keV, 274±10keV, 296±10keV, 338.7±10keV, 389.6±10keV, 429.6±10keV, 530.1±10keV, 507.2±10keV, 665.1±10keV, 727±10keV, 776.6±10keV, 848.2±10keV, 871.1± 10 keV, 962.8 ± 10 keV, 1002 ± 10 keV, 1084 ± 10 keV, 1115 ± 10 keV, 1274 ± 10 keV. Thereby, the accuracy of measuring the neutron dose rate can be further improved.

In some embodiments of the present disclosure, the deterministic functional relationship is a logarithmic function relationship, the logarithmic function relationship being expressed as:

D _i =alnNi+b

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; a, b is a constant And a>0.

In some embodiments of the present disclosure, the deterministic functional relationship is a linear fit function expressed as:

D _i =kN _i +c

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; k, c is a constant And k>0.

According to another aspect of the present disclosure, the present disclosure also provides a neutron dose rate meter having a cesium bromide detector, the cesium bromide detector being adapted to react with incident neutrons A characteristic γ energy peak is generated, and an energy spectrum of the characteristic γ omnipotent peak is detected.

According to the neutron dose rate meter proposed by the present disclosure, by using a cesium bromide detector for a neutron dose rate meter, incident neutrons can be reacted with strontium bromide crystal materials to generate characteristic gamma peaks of different energies, and utilized. The barium bromide detector detects the characteristic gamma peaks produced. Thus, using the neutron dose rate meter proposed by the present disclosure, it is possible to measure the gamma energy peak combination of one or several neutron features and utilize a deterministic function between the neutron dose rate and the net count rate of the characteristic gamma energy peak. Relationship, the measurement of the neutron dose rate in the radiation field.

The additional aspects and advantages of the present disclosure will be set forth in part in the description which follows.

DRAWINGS

The above and/or additional aspects and advantages of the present disclosure will become apparent and readily understood from

1 is a measurement spectrum obtained by measuring a background spectrum measured by a neutron dose rate meter according to an embodiment of the present disclosure and measuring a ²⁵² Cf source.

2 is a measurement spectrum measured in a radiation field of different neutron dose rates using a neutron dose rate meter according to an embodiment of the present disclosure.

3 is a graph of a relationship between a neutron dose rate and a net count rate of a characteristic gamma energy peak, in accordance with an embodiment of the present disclosure.

4 is a graph of a relationship between a neutron dose rate and a net count rate of a characteristic gamma energy peak, in accordance with an embodiment of the present disclosure.

5 is a graph of a relationship between a neutron dose rate and a net count rate of a characteristic gamma energy peak, in accordance with an embodiment of the present disclosure.

6 is a graph of a relationship between a neutron dose rate and a net count rate of a characteristic gamma energy peak, in accordance with an embodiment of the present disclosure.

Public detailed description

The embodiments of the present disclosure are described in detail below, and the examples of the embodiments are illustrated in the drawings, wherein the same or similar reference numerals are used to refer to the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the drawings are illustrative, and are not intended to be construed as limiting.

In accordance with an aspect of the present disclosure, the present disclosure provides a method of measuring a neutron dose rate, which utilizes a neutron characteristic gamma energy peak generated by a neutron in a cesium bromide detector, in accordance with a specific embodiment of the present disclosure. There is a deterministic functional relationship between the net count rate and the neutron dose rate caused by the neutron at this point. By measuring the gamma energy spectrum and using the deterministic functional relationship, the neutron dose rate is calculated and obtained. .

The method for measuring the neutron dose rate according to the present disclosure is actually based on the discovery by the inventors that the net count rate of the neutron characteristic gamma energy peak generated by the neutron in the cesium bromide detector is the same as the neutron There is a deterministic functional relationship between the neutron dose rates caused by the points. In turn, a neutron dose rate meter based on a cesium bromide detector can be used to measure the characteristic gamma peak combination produced by one or several incident neutrons, and between the neutron dose rate and the net count rate of the neutron characteristic gamma peak. A deterministic functional relationship yields a neutron dose rate.

According to a specific implementation of the present disclosure, the method for measuring a neutron dose rate according to the above embodiment includes: detecting a neutron using a ruthenium bromide detector to obtain a characteristic γ energy peak; and calculating the obtained γ energy peak based on the characteristic a sub-dose rate, wherein the neutron dose rate is a deterministic functional relationship with the net count rate of the characteristic gamma energy peak, and the functional relationship can be expressed as:

D _i =f(N _i )

Wherein, D _i is the neutron dose rate, and the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps.

According to the method for measuring the neutron dose rate according to the above embodiment of the present disclosure, one or several characteristic γ energy peaks generated by incident neutrons may be measured by a neutron dose rate meter and a net count of the neutron dose rate and the characteristic γ energy peak may be utilized. The deterministic functional relationship between the rates yields the neutron dose rate at the point of measurement.

According to a specific embodiment of the present disclosure, N _i >0, D _i >0 in the above deterministic function relationship. Thus, the method is more widely applicable.

According to a particular embodiment of the present disclosure, the measured neutron source is generated by a cesium source ( ²⁵² Cf). Thus, the neutron source ( ²⁵² Cf) can be used to generate neutrons of different energies and react with the ytterbium bromide crystals to generate characteristic gamma peaks of different energies, thereby enabling the use of the neutron dose rate and the peak position. The functional relationship between the count rates gives the neutron dose rate.

According to a specific embodiment of the present disclosure, the characteristic gamma energy peak may include, but is not limited to, one selected from the group consisting of: 57.76±5 keV, 83.93±5 keV, 101.8±5 keV, 121.1±5 keV, 174.8±10 keV, 207.9±5 keV 215.6±10 keV. 245.1±10keV, 274±10keV, 296±10keV, 338.7±10keV, 389.6±10keV, 429.6±10keV, 530.1±10keV, 507.2±10keV, 665.1±10keV, 727±10keV, 776.6±10keV, 848.2±10keV, 871.1 ±10 keV, 962.8±10 keV, 1002±10 keV, 1084±10 keV, 1115±10 keV, and 1274±10 keV. Thereby, the accuracy of detecting the neutron dose rate can be further improved.

According to a particular embodiment of the present disclosure, the deterministic functional relationship is a logarithmic function relationship, the logarithmic function relationship being expressed as:

D _i =alnNi+b

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; a, b is a constant And a>0. Thus, through the above functional relationship, the neutron is detected according to the cesium bromide detector, and the net count rate N _{i of the} characteristic γ energy peak is obtained, thereby effectively calculating the neutron dose rate D _i . Therefore, the method of measuring the neutron dose rate of the above-described embodiments of the present disclosure can more easily and quickly determine the neutron dose rate.

According to a particular embodiment of the present disclosure, the deterministic function relationship may be expressed as a linear fit function. The concrete form of the function can be expressed as:

D _i =kN _i +c

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; k, c is a constant And k>0. Thus, through the above functional relationship, the neutron is detected according to the cesium bromide detector, and the net count rate N _{i of the} characteristic γ energy peak is obtained, thereby effectively calculating the neutron dose rate D _i . Therefore, the method of measuring the neutron dose rate of the above-described embodiments of the present disclosure can more easily and quickly determine the neutron dose rate.

According to an aspect of the present disclosure, the present disclosure provides a neutron dose rate meter having a cesium bromide detector, the cesium bromide detector being adapted to react with an incident neutron to generate a characteristic gamma peak, And the energy spectrum of the characteristic γ-all energy peak is detected.

According to the neutron dose rate meter of the above embodiment of the present disclosure, by using the cesium bromide detector for the neutron dose rate meter, the incident neutron can be reacted with the strontium bromide crystal material to generate characteristic gamma peaks of different energies. The characteristic gamma peaks generated by the cesium bromide detector are detected. Thus, the neutron dose rate meter of the above embodiment of the present disclosure can be determined by measuring the combination of one or several neutron characteristic gamma peaks and using the neutron dose rate and the net gamma peak of the characteristic gamma peak. The functional relationship of the sex, the measurement of the neutron dose rate in the radiation field.

According to a specific embodiment of the present disclosure, the working principle of the neutron dose rate meter is: the incident neutron reacts with the strontium bromide crystal material to generate characteristic gamma peaks of different energies, the net count rate of the characteristic gamma peaks and the radiation field. There is a deterministic functional relationship between the neutron dose rates:

D _i =f(N _i )

Wherein, D _i is the neutron dose rate, and the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps. The change in the net count rate of the characteristic gamma peaks of different energies is consistent with the trend of the neutron dose rate. By measuring the net count rate combination of any one or several neutron feature gamma peaks and the corresponding solution calculation, The neutron dose rate of the measured radiation field can be obtained.

The specific embodiments of the present disclosure will be described in detail below with reference to the drawings and specific embodiments. In the following description, numerous specific details are set forth in the However, the present disclosure can be implemented in many other ways than those described herein, and those skilled in the art can make similar modifications without departing from the scope of the present disclosure, and thus the present disclosure is not limited by the specific embodiments disclosed below.

Example 1

The neutron dose rate was measured using a neutron dose rate meter. Among them, the neutron dose rate meter has a cesium bromide detector, and the cesium bromide detector uses a 2in × 2in cesium bromide detector (CeBr ₃ ). The source of the neutron to be tested is selected from the source (Cf-252 source).

The characteristic γ energy peaks generated by the reaction of ²⁵² Cf source with strontium bromide crystals include, but are not limited to, the energy values listed in Table 1; Table 2 shows the energy of the characteristic γ energy peaks generated by the reaction of neutrons with strontium bromide crystals, The net count rate of the characteristic gamma energy peak and the neutron dose rate, the characteristic gamma energy peaks include but are not limited to the four energies listed in Table 2.

The background spectrum measured by the neutron dose rate meter and the measured spectrum obtained by measuring the ²⁵² Cf source are shown in Fig. 1; Fig. 2 is the gamma energy spectrum detected by the neutron dose rate meter when measuring different neutron dose rates. The neutron dose rate includes but is not limited to the seven dose rate levels listed in Figure 2; Figure 3 shows the relationship between the neutron dose rate and the characteristic gamma peak peak count rate, including but not limited to The seven dose rate levels described in Figure 3, the characteristic gamma energy peaks include, but are not limited to, the four energies listed in Figure 3. 4 is a relationship between the neutron dose rate and the characteristic γ energy peak net count rate after normalization according to the maximum value of each energy peak net count rate, and the neutron dose rate includes but is not limited to FIG. At seven dose rate levels, the characteristic gamma energy peaks include, but are not limited to, the four energies listed in Figure 4. 5 is a relationship between the neutron dose rate and the characteristic γ energy peak net count rate when the characteristic γ peak is taken as a peak of 121.1 keV. The function relationship is a logarithmic function relationship, and the neutron dose rate includes but is not limited to FIG. For the seven dose rate levels, the characteristic gamma energy peaks include, but are not limited to, the energy listed in FIG. Fig. 6 is a graph showing the relationship between the neutron dose rate and the characteristic gamma peak peak count rate when the characteristic γ peak is 119.2 keV. The functional relationship is a linear fit function. The neutron dose rate includes but is not limited to Fig. 6. The seven dose rate levels, characteristic gamma energy peaks include, but are not limited to, the energy listed in FIG.

Table 1 Characteristic γ energy peaks produced by the reaction of ²⁵² Cf source with strontium bromide crystals

Serial number	Peak energy (keV)
1	57.76
2	83.93
3	101.8
4	121.1
5	174.8
6	207.9
7	215.6
8	245.1
9	274
10	296
11	338.7
12	389.6
13	429.6
14	530.1
15	607.2

16	665.1
17	727
18	776.6
19	848.2
20	871.1
twenty one	962.8
twenty two	1002
twenty three	1084
twenty four	1115
25	1274

Table 2 Energy of γ-energy peaks, net count rate of characteristic γ-energy peaks and neutron dose rate

According to the measured results of Fig. 3 and Fig. 4, it can be seen that the deterministic functional relationship between the net count rate of the characteristic γ energy peak generated by the reaction of neutrons with strontium bromide crystals and the neutron dose rate can be expressed as a logarithmic function. . The concrete form of the function can be expressed as:

D _i =alnNi+b

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; a, b is a constant And a>0. For example, in Fig. 5, when the characteristic γ peak takes a peak of 121.1 keV, the neutron dose rate is logarithmically a function of the net gamma energy peak count rate. The change of the net count rate of the characteristic γ energy peaks of different energies is consistent with the change trend of the neutron dose rate, that is, by measuring the net count rate combination of any one or several neutron characteristic γ energy peaks, the measured value can be obtained. The neutron dose rate of the radiation field.

According to the measured results of Fig. 3 and Fig. 4, it can be seen that the deterministic function relationship between the net count rate of the characteristic γ energy peak generated by the reaction of neutrons with strontium bromide crystals and the neutron dose rate can be expressed as a linear fit. function. The concrete form of the function can be expressed as:

D _i =kN _i +c

Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; k, c is a constant And k>0. For example, in Fig. 6, when the characteristic γ peak takes a peak of 121.1 keV, the neutron dose rate has a linear fitting function relationship with the characteristic γ energy peak net count rate. The change of the net count rate of the characteristic γ energy peaks of different energies is consistent with the change trend of the neutron dose rate, that is, by measuring the net count rate combination of any one or several neutron characteristic γ energy peaks, the measured value can be obtained. The neutron dose rate of the radiation field.

In the description of the present specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" and the like means a specific feature described in connection with the embodiment or example. A structure, material, or feature is included in at least one embodiment or example of the present disclosure. In the present specification, the schematic representation of the above terms is not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in a suitable manner in any one or more embodiments or examples. In addition, various embodiments or examples described in the specification, as well as features of various embodiments or examples, may be combined and combined.

While the embodiments of the present disclosure have been shown and described above, it is understood that the foregoing embodiments are illustrative and are not to be construed as limiting the scope of the disclosure The embodiments are subject to variations, modifications, substitutions and variations.

Claims (9)

1. A method of measuring a neutron dose rate, wherein the method utilizes a net count rate of a neutron characteristic gamma energy peak produced by a neutron in a ruthenium bromide detector and a neutron dose caused by the neutron at the point There is a deterministic functional relationship between the rates, and the neutron dose rate is calculated and obtained by measuring the gamma energy spectrum and using the deterministic functional relationship.
2. The method of claim 1 comprising:

   The neutron is detected by a cesium bromide detector to obtain a characteristic gamma peak;

   Calculating a neutron dose rate based on the characteristic gamma energy peak, wherein the neutron dose rate is a deterministic functional relationship with the net gamma energy peak of the characteristic gamma energy peak, and the functional relationship can be expressed as:

   D _i =f(N _i )

   Wherein, D _i is the neutron dose rate, and the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps.
3. The method of claim 2, wherein in the deterministic functional relationship, the net count rate ranges from: N _i >
4. The method according to claim 2 or 3, wherein in the deterministic functional relationship, the measurement range of the neutron dose rate is: D _i >
5. A method according to any one of claims 1 to 4, wherein the neutrons are produced by a cesium source.
6. The method according to any one of claims 1 to 5, wherein the characteristic gamma energy peak comprises at least one selected from the group consisting of 57.76 ± 5 keV, 83.93 ± 5 keV, 101.8 ± 5 keV, 121.1 ± 5 keV, 174.8 ± 10 keV. 207.9±5keV215.6±10keV, 245.1±10keV, 274±10keV, 296±10keV, 338.7±10keV, 389.6±10keV, 429.6±10keV, 530.1±10keV, 507.2±10keV, 665.1±10keV, 727±10keV, 776.6 ±10 keV, 848.2 ± 10 keV, 871.1 ± 10 keV, 962.8 ± 10 keV, 1002 ± 10 keV, 1084 ± 10 keV, 1115 ± 10 keV, 1274 ± 10 keV.
7. The method of any of claims 1-6, wherein the deterministic functional relationship is a logarithmic function relationship, the logarithmic function relationship being expressed as:

   D _i =alnNi+b

   Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; a, b is a constant And a>0.
8. The method of any of claims 1-6, wherein the deterministic functional relationship is a linear fit function, the linear fit function being expressed as:

   D _i =kN _i +c

   Where D _i is the neutron dose rate, the unit is μSv/h; N _i is the net count rate of the characteristic γ energy peak generated by the reaction of the incident neutron with the cesium bromide crystal material, the unit is cps; k, c is a constant And k>0.
9. A neutron dose rate meter, wherein the neutron dose rate meter has a cesium bromide detector, and the cesium bromide detector is adapted to react with an incident neutron to generate a characteristic gamma energy peak, and detect a characteristic γ The spectrum of the omnipotent peak.

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