WO2019109812A9 - 利用溴化镧探测器测量中子剂量率的方法和中子剂量率仪 - Google Patents

利用溴化镧探测器测量中子剂量率的方法和中子剂量率仪 Download PDF

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WO2019109812A9
WO2019109812A9 PCT/CN2018/116973 CN2018116973W WO2019109812A9 WO 2019109812 A9 WO2019109812 A9 WO 2019109812A9 CN 2018116973 W CN2018116973 W CN 2018116973W WO 2019109812 A9 WO2019109812 A9 WO 2019109812A9
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neutron
dose rate
neutron dose
characteristic
10kev
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WO2019109812A1 (zh
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曾志
刘翠红
李君利
张辉
曾鸣
马豪
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清华大学
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    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation

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  • 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.
  • the neutron dose rate meter is a radiation monitoring device for measuring and evaluating the surrounding dose equivalent rate produced by neutron radiation.
  • 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.
  • 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
  • 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 such as 3 He
  • 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.
  • Barium bromide detector is a new type of inorganic scintillation detector with excellent time resolution (hundreds of picoseconds), high energy resolution ( ⁇ 3%, for 662keV gamma rays) and high detection efficiency. Measured by gamma spectroscopy.
  • the cesium bromide detector is mainly composed of strontium bromide crystal.
  • the constituent elements mainly include La and Br. Considering the abundance of natural isotopes, mainly 139 La, 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.
  • the neutron kinetic energy is sufficient to excite the target nucleus and the inelastic scattering A(n,n' ⁇ )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, the target nucleus
  • gamma rays are emitted, for example, 79 Br(n, n' ⁇ ) 79m Br, 79m Br de-excitation emits ⁇ -ray energy of 217keV; if radiation capture reaction A(n, ⁇ )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, 139 La (n, ⁇ ) 140 La, 140 La to ⁇ - form of the decay of 140 Ce; 79 Br (n, ⁇ ) 80 Br, 80 Br to ⁇ - manner and orbital electron capture Decay to 80 Kr; 81 Br(n, ⁇ ) 82 Br, 82 Br decays to 82 Kr in a ⁇ - form.
  • the gamma rays of different energies produced by the nuclear reaction can be detected and resolved by the cesium bromide detector.
  • the detection of neutrons by the cesium bromide detector can be realized, for example, for 700keV
  • the detection efficiency of the neutron, 2in ⁇ 2in cesium bromide detector can reach 5%. This detection efficiency is superior to other types of neutron detectors from the detector itself.
  • the above detection method is based on the time of flight method and is not suitable for the field of radiation protection.
  • the time-of-flight method is based on different energy (flight speed) neutrons flying over a certain distance
  • the measurement of neutron energy is converted to the time required to fly the selected distance of the neutron, by measurement Time distribution to determine the neutron energy distribution.
  • This method requires extremely accurate recording of the starting and ending moments of neutrons over the flight distance, which is clearly not achievable in the field of radiation protection.
  • the present disclosure proposes a neutron dose rate meter based on a cesium bromide detector for neutron dose rate measurement in the field of radiation protection.
  • 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 have unexpectedly discovered that the change in the net count rate of the characteristic gamma peaks of different energies produced by the reaction of neutrons with strontium bromide crystal material is consistent with the trend of neutron dose rate, using neutron dose rate and characteristic ⁇ .
  • the deterministic functional relationship between the net count rates of the energy peaks can be measured by measuring the net count rate combination and the spectrum calculation of one or several neutron characteristic gamma peaks to achieve the measurement of the neutron dose rate in the radiation field.
  • 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.
  • 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.
  • 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.
  • the method of measuring a neutron dose rate comprises:
  • the neutron is detected by a cesium bromide detector to obtain a characteristic gamma peak
  • D i is the neutron dose rate, and the unit is ⁇ Sv/h; N i is the net count rate of the characteristic ⁇ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps.
  • the net count rate ranges from: N i >0.
  • the neutron dose rate is measured in a range of: D i >0.
  • the neutron is generated by a source of germanium.
  • 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 is generated by a source of germanium.
  • the characteristic gamma energy peak comprises at least one selected from the group consisting of: 22.34 ⁇ 5 keV, 54.64 ⁇ 5 keV, 83.05 ⁇ 5 keV, 101.1 ⁇ 5 keV, 119.2 ⁇ 5 keV, 166.5 ⁇ 5 keV, 207.1 ⁇ 5 keV.
  • the deterministic functional relationship is a logarithmic function relationship, the logarithmic function relationship being expressed as:
  • D i is the neutron dose rate
  • the unit is ⁇ Sv/h
  • N i is the net count rate of the characteristic ⁇ 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.
  • the deterministic functional relationship is a linear fit function expressed as:
  • D i is the neutron dose rate
  • the unit is ⁇ Sv/h
  • N i is the net count rate of the characteristic ⁇ 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.
  • 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 ⁇ energy peak is generated, and an energy spectrum of the characteristic ⁇ omnipotent peak is detected.
  • 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.
  • 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.
  • 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.
  • FIG. 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.
  • FIG 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.
  • FIG. 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.
  • FIG. 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.
  • FIG. 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.
  • 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.
  • a neutron dose rate which utilizes a neutron characteristic gamma energy peak generated by a neutron in a cesium bromide detector.
  • 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.
  • 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.
  • the method for measuring a neutron dose rate includes: detecting a neutron using a ruthenium bromide detector to obtain a characteristic ⁇ energy peak; and calculating the obtained ⁇ 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 is the neutron dose rate, and the unit is ⁇ Sv/h; N i is the net count rate of the characteristic ⁇ energy peak generated by the nuclear reaction between the incident neutron and the cesium bromide crystal material, and the unit is cps.
  • one or several characteristic ⁇ 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 ⁇ energy peak may be utilized.
  • the deterministic functional relationship between the rates yields the neutron dose rate at the point of measurement.
  • the method is more widely applicable.
  • the measured neutron is generated by a source ( 252 Cf).
  • 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.
  • the characteristic gamma energy peak may include, but is not limited to, one selected from the group consisting of: 22.34 ⁇ 5 keV, 54.64 ⁇ 5 keV, 83.05 ⁇ 5 keV, 101.1 ⁇ 5 keV, 119.2 ⁇ 5 keV, 166.5 ⁇ 5 keV, 207.1 ⁇ 5keV, 217.5 ⁇ 5keV, 243.3 ⁇ 5keV, 262 ⁇ 5keV, 276.7 ⁇ 5keV, 294.9 ⁇ 5keV, 307.2 ⁇ 5keV, 335 ⁇ 5keV, 344 ⁇ 5keV, 387.9 ⁇ 5keV, 536.9 ⁇ 10keV, 606.9 ⁇ 10keV, 650.5 ⁇ 5keV, 725.1 ⁇ 10keV, 766.8 ⁇ 10keV 842.7 ⁇ 10keV, 872.4 ⁇ 10keV, 962.8 ⁇ 10keV, 1002 ⁇ 10keV, 1043 ⁇ 10keV, 1084 ⁇ 10keV, 1115 ⁇ 10keV, 12
  • the deterministic functional relationship is a logarithmic function relationship, the logarithmic function relationship being expressed as:
  • D i is the neutron dose rate
  • the unit is ⁇ Sv/h
  • N i is the net count rate of the characteristic ⁇ 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.
  • the deterministic function relationship may be expressed as a linear fit function.
  • the concrete form of the function can be expressed as:
  • the neutron is detected according to the cesium bromide detector, and the net count rate N i of the characteristic ⁇ 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.
  • 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 ⁇ -all energy peak is detected.
  • 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.
  • 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.
  • 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.
  • the neutron dose rates There is a deterministic functional relationship between the neutron dose rates:
  • D i is the neutron dose rate, and the unit is ⁇ Sv/h;
  • N i is the net count rate of the characteristic ⁇ 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.
  • the neutron dose rate was measured using a neutron dose rate meter.
  • the neutron dose rate meter has a cesium bromide detector, and the cesium bromide detector uses a 3in ⁇ 3in cesium bromide detector (LaBr 3 :Ce).
  • the source of the neutron to be tested is selected from the source (Cf-252 source).
  • the characteristic ⁇ 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 ⁇ 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 five energies listed in Table 2.
  • Fig. 1 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.
  • the neutron dose rate includes but is not limited to the graph. 3
  • the seven dose rate levels, the characteristic gamma energy peaks include but are not limited to the five energies listed in FIG.
  • the characteristic gamma energy peaks include, but are not limited to, the four energies listed in Figure 4.
  • Figure 5 is a graph showing the relationship between the neutron dose rate and the characteristic gamma peak peak count rate when the characteristic ⁇ peak is 119.2 keV. The functional relationship is logarithmically related.
  • the neutron dose rate includes but is not limited to Figure 5.
  • the characteristic gamma energy peaks include, but are not limited to, the energy listed in FIG. Fig.
  • 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.
  • D i is the neutron dose rate
  • the unit is ⁇ Sv/h
  • N i is the net count rate of the characteristic ⁇ 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.
  • 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 ⁇ 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 ⁇ energy peaks, the measured value can be obtained.
  • the neutron dose rate of the radiation field 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 ⁇ energy peaks, the measured value can be obtained.
  • the neutron dose rate has a linear fitting function relationship with the characteristic ⁇ energy peak net count rate.
  • the change of the net count rate of the characteristic ⁇ 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 ⁇ energy peaks, the measured value can be obtained.
  • the neutron dose rate of the radiation field when the characteristic ⁇ peak is taken as the peak of 119.2 keV, the neutron dose rate has a linear fitting function relationship with the characteristic ⁇ energy peak net count rate.
  • the change of the net count rate of the characteristic ⁇ energy peaks of different energies is consistent with the change trend of the neutron dose rate

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Abstract

利用溴化镧探测器测量中子剂量率的方法和中子剂量率仪，其中，测量中子剂量率的方法利用中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与中子在该点造成的中子剂量率之间存在确定性的函数关系，通过测量γ能谱，并利用确定性的函数关系，计算并获得中子剂量率。

Description

利用溴化镧探测器测量中子剂量率的方法和中子剂量率仪 技术领域
本公开属于辐射探测、环境监测设备技术领域，具体而言，本公开涉及利用溴化镧探测器测量中子剂量率的方法和中子剂量率仪。
背景技术
中子剂量率仪是一种用于测量和评价中子辐射产生的周围剂量当量率的辐射监测设备。目前，常见的辐射防护用中子剂量率仪，其基本组成包括慢化体、中子能量补偿材料、热中子灵敏计数器及电子学线路。其结构特点是将热中子灵敏计数器用球形或圆柱形慢化体裹在中心处；慢化体内，离中心探测器某一距离上设置一带有慢中子透过孔的中子吸收筛，或用含硼材料的吸收层，入射中子射入慢化体后被慢化(或热中子扩散)，在通过吸收筛(或吸收层)时一部分慢(热)中子被吸收，一定比例的中子穿过，穿过吸收筛的部分中子继续被慢化或扩散，最后到达中心探测器的部分中子被探测记录下来。
现有的中子剂量率仪，根据结构设计的不同，可大致分为三类：一是单计数器型，这类剂量率仪采用单个球形或柱形聚乙烯作为慢化体，球心放置单个正比计数器(如BF 3、 3He)或 6Li玻璃闪烁体，球体中间夹杂一些经过特殊设计的硼塑料或镉材料等中子能量补偿材料。二是多计数器型，这类剂量率仪的慢化体为单球或多球设计，探头采用多个正比计数器(如 3He)，分别放置在慢化体的球心或者球面，球体中间夹杂中子能量补偿材料。三是谱仪型，这类剂量率仪将热中子探测器分别包裹在不同直径的慢化球壳内，利用不同大小慢化球的慢化能力不同，得到不同能量的中子响应，通过对测量得到的慢化中子能谱进行解谱，解出中子辐射场的实际能谱，进而计算得到辐射场的中子剂量率。
溴化镧探测器是一种新型的无机闪烁体探测器，具有优秀的时间分辨率(数百皮秒)、高能量分辨率(<3％，对于662keVγ射线)和高探测效率，被广泛应用于γ能谱测量。作为无机闪烁体型探测器，溴化镧探测器主要由溴化镧晶体组成，组成元素主要包括La和Br，从天然同位素丰度考虑，主要是 139La， 79Br和 81Br，三种核素均为稳定核素。但当中子入射到溴化镧晶体材料时，中子会与靶物质核素发生核反应，主要反应类型包括弹性散射、非弹性散射和辐射俘获。其中，如果中子动能足以激发靶核，发生非弹性散射A(n，n′γ)A′， 那么入射中子会将初始动能的一部分传递给原子核，使靶核激发到激发态，靶核退激时放出γ射线，例如 79Br(n，n′γ) 79mBr， 79mBr退激会放出能量为217keV的γ射线；如果发生辐射俘获反应A(n,γ)B，那么靶核俘获中子，产生新的靶核，新核通常处于不稳定的激发状态，激发能取决于中子的结合能与动能，受激核会通过发射一个或数个γ量子而跃迁回基态，且会发射后续的放射性衰变，例如 139La(n,γ) 140La， 140La以β -的形式衰变为 140Ce； 79Br(n,γ) 80Br， 80Br以β -和轨道电子俘获的方式衰变为 80Kr； 81Br(n,γ) 82Br， 82Br以β -的方式衰变为 82Kr。核反应所产生的不同能量的γ射线，可被溴化镧探测器探测并分辨。
近年来，随着研究的深入，国外研究者通过实验研究发现，利用上述核反应产生γ射线的物理机制，采用飞行时间法，可实现溴化镧探测器对中子的探测，例如，对于700keV的中子，2in×2in溴化镧探测器的探测效率可达5％。单从探测器本身而言，该探测效率是优于其他类型的中子探测器的。但上述探测方法是基于飞行时间法，并不适用于辐射防护领域。因为飞行时间法是基于不同能量(飞行速度)的中子飞越某一确定距离所需时间不同，将对中子能量的测量转换为对该中子飞越选定距离所需时间的测量，通过测量时间分布，从而确定中子能量分布。该方法需要极为精确地记录中子在飞行距离上的起点时刻和终点时刻，这在辐射防护领域显然是无法实现的。
因此，本公开提出一种基于溴化镧探测器的中子剂量率仪，用于辐射防护领域的中子剂量率测量。
公开内容
本公开旨在至少在一定程度上解决相关技术中的技术问题之一。为此，本公开的一个目的在于提出测量中子剂量率的方法和中子剂量率仪，采用本公开提出的测量中子剂量率的方法，该方法利用溴化镧探测器可以与入射中子发生反应，产生不同能量的特征γ能峰，并利用溴化镧探测器进行探测与分辨，进而可以利用中子剂量率与特征γ能峰的净计数率之间确定性的函数关系得到中子剂量率。
发明人发现，采用飞行时间法可以实现溴化镧探测器对中子的探测，但是通过精确记录中子在选定飞行距离上的起点时刻和终点时刻来确定中子能量分布在辐射防护领域是无法实现的，飞行时间法并不适用于辐射防护领域。发明人意外发现，中子与溴化镧晶体材料发生反应产生的不同能量的特征γ能峰的净计数率的变化与中子剂量率的变化趋势是一 致的，利用中子剂量率与特征γ能峰的净计数率之间确定性的函数关系，可以通过测量一个或几个中子特征γ能峰的净计数率组合与解谱计算，实现辐射场中子剂量率的测量。
为此，根据本公开的第一个方面，本公开提出了一种测量中子剂量率的方法，根据本公开的具体实施例，所述方法利用中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与所述中子在该点造成的中子剂量率之间存在确定性的函数关系，通过测量γ能谱，并利用所述确定性的函数关系，计算并获得中子剂量率。
根据本公开提出的测量中子剂量率的方法，实际上是基于发明人发现了，中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与所述中子在该点造成的中子剂量率之间存在确定性的函数关系。进而可以采用基于溴化镧探测器的中子剂量率仪测量一个或几个入射中子产生的特征γ能峰组合，并利用中子剂量率与中子特征γ能峰的净计数率之间确定性的函数关系得到中子剂量率。
在本公开的一些实施例中，所述测量中子剂量率的方法包括：
采用溴化镧探测器对中子进行探测，以便获得特征γ能峰；
基于所述特征γ能峰，计算获得中子剂量率，其中，所述中子剂量率与所述特征γ能峰的净计数率呈确定性的函数关系，函数关系可表示为：
D i＝f(N i)
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生核反应产生的特征γ能峰的净计数率，单位为cps。
在本公开的一些实施例中，所述确定性的函数关系中，所述净计数率的范围为：N i>0。
在本公开的一些实施例中，所述确定性的函数关系中，所述中子剂量率的测量范围为：D i>0。
在本公开的一些实施例中，所述中子由锎源产生。由此，可以产生不同能量的中子，并与溴化镧晶体发生反应，进而产生不同能量的特征γ能峰，进而能够利用中子剂量率与峰位的净计数率之间的函数关系得到中子剂量率。
在本公开的一些实施例中，所述特征γ能峰包括选自下列至少之一：22.34±5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、166.5±5keV、207.1±5keV、217.5±5keV、243.3±5keV、276.7±5keV、294.9±5keV、307.2±5keV、335±5keV、344±5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±5keV、725.1±10keV、766.8±10keV 842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、1043±10keV、1084±10keV、1115±10keV、1268±10keV。由此，可以进一步提高测量中子剂量率的精准度。
在本公开的一些实施例中，所述确定性的函数关系为对数函数关系，所述对数函数关系表示为：
D i＝alnNi+b
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；a，b为常数，且a>0。
在本公开的一些实施例中，所述确定性的函数关系为线性拟合函数，所述线性拟合函数表示为：
D i＝kN i+c
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；k，c为常数，且k>0。
根据本公开的另一个方面，本公开还提出了一种中子剂量率仪，所述中子剂量率仪具有溴化镧探测器，所述溴化镧探测器适于与入射中子发生反应产生特征γ能峰，并探测得到特征γ全能峰的能谱。
根据本公开提出的中子剂量率仪，通过将溴化镧探测器用于中子剂量率仪，可以使入射中子与溴化镧晶体材料发生反应，产生不同能量的特征γ能峰，并利用溴化镧探测器对产生的特征γ能峰进行探测。由此，采用本公开提出的中子剂量率仪，可以通过测量一个或几个中子特征γ能峰组合，并利用中子剂量率与特征γ能峰的净计数率之间确定性的函数关系，实现辐射场中子剂量率的测量。
本公开的附加方面和优点将在下面的描述中部分给出，部分将从下面的描述中变得明显，或通过本公开的实践了解到。
附图说明
本公开的上述和/或附加的方面和优点从结合下面附图对实施例的描述中将变得明显和容易理解，其中：
图1是利用本公开一个实施例的中子剂量率仪测量得到的本底谱和测量 252Cf源得到的测量谱图。
图2是利用本公开一个实施例的中子剂量率仪在不同中子剂量率的辐射场中测量得到的测量谱图。
图3是根据本公开一个实施例的中子剂量率与特征γ能峰的净计数率之间的关系图。
图4是根据本公开一个实施例的中子剂量率与特征γ能峰的净计数率之间的关系图。
图5是根据本公开一个实施例的中子剂量率与特征γ能峰的净计数率之间的关系图。
图6是根据本公开一个实施例的中子剂量率与特征γ能峰的净计数率之间的关系图。
公开详细内容
下面详细描述本公开的实施例，所述实施例的示例在附图中示出，其中自始至终相同或类似的标号表示相同或类似的元件或具有相同或类似功能的元件。下面通过参考附图描述的实施例是示例性的，旨在用于解释本公开，而不能理解为对本公开的限制。
根据本公开的一个方面，本公开提出了一种测量中子剂量率的方法，根据本公开的具体实施例，所述方法利用中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与所述中子在该点造成的中子剂量率之间存在确定性的函数关系，通过测量γ能谱，并利用所述确定性的函数关系，计算并获得中子剂量率。
根据本公开提出的测量中子剂量率的方法，实际上是基于发明人发现了，中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与所述中子在该点造成的中子剂量率之间存在确定性的函数关系。进而可以采用基于溴化镧探测器的中子剂量率仪测量一个或几个入射中子产生的特征γ能峰组合，并利用中子剂量率与中子特征γ能峰的净计数率之间确定性的函数关系得到中子剂量率。
根据本公开的具体实施，上述实施例的测量中子剂量率的方法包括：采用溴化镧探测器对中子进行探测，以便获得特征γ能峰；基于所述特征γ能峰，计算获得中子剂量率，其中，所述中子剂量率与所述特征γ能峰的净计数率呈确定性的函数关系，函数关系可表示为：
D i＝f(N i)
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生核反应产生的特征γ能峰的净计数率，单位为cps。
根据本公开上述实施例的测量中子剂量率的方法，可以采用中子剂量率仪测量入射中 子产生的一个或几个特征γ能峰并利用中子剂量率与特征γ能峰的净计数率之间确定性的函数关系得到被测点位的中子剂量率。
根据本公开的具体实施例，上述确定性函数关系中的N i>0，D i>0。由此，该方法适用范围更广泛。
根据本公开的具体实施例，被测中子由锎源( 252Cf)产生。由此，可以利用锎源( 252Cf)可产生不同能量的中子，并与溴化镧晶体发生反应，进而产生不同能量的特征γ能峰，进而能够利用中子剂量率与峰位的净计数率之间的函数关系得到中子剂量率。
根据本公开的具体实施例，特征γ能峰可以包括但不限定于选自下列之一：22.34±5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、166.5±5keV、207.1±5keV、217.5±5keV、243.3±5keV、262±5keV、276.7±5keV、294.9±5keV、307.2±5keV、335±5keV、344±5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±5keV、725.1±10keV、766.8±10keV 842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、1043±10keV、1084±10keV、1115±10keV、1268±10keV。
根据本公开的具体实施例，所述确定性的函数关系为对数函数关系，所述对数函数关系表示为：
D i＝alnNi+b
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；a，b为常数，且a>0。由此通过上述函数关系式，根据溴化镧探测器对中子进行探测，获得特征γ能峰的净计数率N i，进而有效计算出中子剂量率D i。因此，本公开上述实施例的测量中子剂量率的方法可以更加方便快速地测定中子剂量率。
根据本公开的具体实施例，所述确定性函数关系，可表示为线性拟合函数。函数的具体形式可表示为：
D i＝kN i+c
其中，D i为中子剂量率，μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；k，c为常数，且k>0。由此通过上述函数关系式，根据溴化镧探测器对中子进行探测，获得特征γ能峰的净计数率N i，进而有效计算出中子剂量率D i。因此，本公开上述实施例的测量中子剂量率的方法可以更加方便快速地测定中子剂量 率。
根据本公开的一个方面，本公开提出了一种中子剂量率仪，中子剂量率仪具有溴化镧探测器，溴化镧探测器适于与入射中子发生反应产生特征γ能峰，并探测得到特征γ全能峰的能谱。
根据本公开上述实施例的中子剂量率仪，通过将溴化镧探测器用于中子剂量率仪，可以使入射中子与溴化镧晶体材料发生反应，产生不同能量的特征γ能峰，并利用溴化镧探测器对产生的特征γ能峰进行探测。由此，采用本公开上述实施例的中子剂量率仪，可以通过测量一个或几个中子特征γ能峰的组合，并利用中子剂量率与特征γ能峰的净计数率之间确定性的函数关系，实现辐射场中子剂量率的测量。
根据本公开的具体实施例，中子剂量率仪的工作原理为：入射中子与溴化镧晶体材料发生反应，产生不同能量的特征γ能峰，特征γ能峰的净计数率与辐射场的中子剂量率之间存在确定性的函数关系，为：
D i＝f(N i)
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生核反应产生的特征γ能峰的净计数率，单位为cps。不同能量的特征γ能峰的净计数率的变化与中子剂量率的变化趋势是一致的，通过测量任何一个或几个中子特征γ能峰的净计数率组合与相应的解谱计算，均可得到被测辐射场的中子剂量率。
为使本公开的上述目的、特征和优点能够更加明显易懂，下面结合附图和具体实施例对本公开的具体实施方式做详细的说明。在下面的描述中阐述了很多具体细节以便于充分理解本公开。但是本公开能够以很多不同于在此描述的其它方式来实施，本领域技术人员可以在不违背本公开内涵的情况下做类似改进，因此本公开不受下面公开的具体实施的限制。
实施例1
采用中子剂量率仪测量中子剂量率。其中，中子剂量率仪具有溴化镧探测器，溴化镧探测器采用3in×3in溴化镧探测器(LaBr 3:Ce)。待测中子源选取锎源(Cf-252源)。
252Cf源与溴化镧晶体发生反应产生的特征γ能峰包括但不限定于表1列出的能量值；表2为中子与溴化镧晶体发生反应产生的特征γ能峰的能量、特征γ能峰的净计数率与中 子剂量率，特征γ能峰包括但不限定于表2所列的5个能量。
采用中子剂量率仪测量得到的本底谱和测量 252Cf源得到的测量谱如图1所示；图2为测量不同中子剂量率时中子剂量率仪探测得到的伽马能谱，中子剂量率包括但不限定于图2所列的7种剂量率水平；图3为中子剂量率与特征γ能峰净计数率之间的关系，中子剂量率包括但不限定于图3所述7种剂量率水平，特征γ能峰包括但不限定于图3所列5种能量。图4为按照各个能峰净计数率的最大值进行归一化处理后，中子剂量率与特征γ能峰净计数率之间的关系，中子剂量率包括但不限定于图4所述7种剂量率水平，特征γ能峰包括但不限定于图4所列4种能量。图5为特征γ峰取119.2keV峰时，中子剂量率与特征γ能峰净计数率之间的关系，该函数关系呈对数函数关系，中子剂量率包括但不限定于图5所述7种剂量率水平，特征γ能峰包括但不限定于图5所列能量。图6为特征γ峰取119.2keV峰时，中子剂量率与特征γ能峰净计数率之间的关系，该函数关系呈线性拟合函数关系，中子剂量率包括但不限定于图6所述7种剂量率水平，特征γ能峰包括但不限定于图6所列能量。
表1  252Cf源与溴化镧晶体发生反应产生的特征γ能峰
序号 能峰值(keV)
1 22.34
2 54.64
3 83.05
4 101.1
5 119.2
6 166.5
7 207.1
8 217.5
9 243.3
10 262.0
11 276.7
12 294.9
13 307.2
14 335.0
15 344.0
16 387.9
17 536.9
18 606.9
19 650.5
20 725.1
21 766.8
22 842.7
23 872.4
24 962.8
25 1002.0
26 1043.0
27 1084.0
28 1115.0
29 1268.0
表2中子特征γ能峰的能量、特征γ能峰的净计数率与中子剂量率
Figure PCTCN2018116973-appb-000001
根据图3和图4的实测结果可以看出，中子与溴化镧晶体发生反应产生的特征γ能峰的净计数率与中子剂量率之间的确定性函数关系可表示为对数函数。函数的具体形式可表示为：
D i＝alnNi+b
其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；a，b为常数，且a>0。例如，图5为特征γ峰取119.2keV峰时，中子剂量率与特征γ能峰净计数率呈对数函数关系。不同能量的特征γ能峰的净计数率的变化与中子剂量率的变化趋势是一致的，即通过测量任何一个或几个中子特征γ能峰的净计数率组合，均可得到被测辐射场的中子剂量率。
根据图3和图4的实测结果可以看出，中子与溴化镧晶体发生反应产生的特征γ能峰的净计数率与中子剂量率之间的确定性函数关系可表示为线性拟合函数。函数的具体形式可表示为：
D i＝kN i+c
其中，D i为中子剂量率，μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；k，c为常数，且k>0。例如，图6为特征γ峰取119.2keV峰时，中子剂量率与特征γ能峰净计数率呈线性拟合函数关系。不同能量的特征γ能峰的净计数率的变化与中子剂量率的变化趋势是一致的，即通过测量任何一个或几个中子特征γ能峰的净计数率组合，均可得到被测辐射场的中子剂量率。
在本说明书的描述中，参考术语“一个实施例”、“一些实施例”、“示例”、“具体示例”、或“一些示例”等的描述意指结合该实施例或示例描述的具体特征、结构、材料或者特点包含于本公开的至少一个实施例或示例中。在本说明书中，对上述术语的示意性表述不必针对的是相同的实施例或示例。而且，描述的具体特征、结构、材料或者特点可以在任一个或多个实施例或示例中以合适的方式结合。此外，在不相互矛盾的情况下，本领域的技术人员可以将本说明书中描述的不同实施例或示例以及不同实施例或示例的特征进行结合和组合。
尽管上面已经示出和描述了本公开的实施例，可以理解的是，上述实施例是示例性的，不能理解为对本公开的限制，本领域的普通技术人员在本公开的范围内可以对上述实施例进行变化、修改、替换和变型。

Claims (9)

  1. 一种测量中子剂量率的方法，其中，所述方法利用中子在溴化镧探测器中产生的中子特征γ能峰的净计数率与所述中子在该点造成的中子剂量率之间存在确定性的函数关系，通过测量γ能谱，并利用所述确定性的函数关系，计算并获得中子剂量率。
  2. 根据权利要求1所述的方法，其中，包括：
    采用溴化镧探测器对中子进行探测，以便获得特征γ能峰；
    基于所述特征γ能峰，计算获得中子剂量率，其中，所述中子剂量率与所述特征γ能峰的净计数率呈确定性的函数关系，函数关系可表示为：
    D i＝f(N i)
    其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生核反应产生的特征γ能峰的净计数率，单位为cps。
  3. 根据权利要求2所述的方法，其中，所述确定性的函数关系中，所述净计数率的范围为：N i>0。
  4. 根据权利要求2或3所述的方法，其中，所述确定性的函数关系中，所述中子剂量率的测量范围为：D i>0。
  5. 根据权利要求1-4中任一项所述的方法，其中，所述中子由锎源产生。
  6. 根据权利要求1-5中任一项所述的方法，其中，所述特征γ能峰包括选自下列至少之一：22.34±5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、173.5±5keV、207.1±5keV、217.5±5keV、243.3±5keV、262±5keV、276.7±5keV、294.9±5keV、307.2±5keV、335±5keV、344±5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±10keV、725.1±10keV、766.8±10keV 842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、1043±10keV、1084±10keV、1115±10keV、1268±10keV。
  7. 根据权利要求1-6中任一项所述的方法，其中，所述确定性的函数关系为对数函数关系，所述对数函数关系表示为：
    D i＝alnNi+b
    其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；a，b为常数，且a>0。
  8. 根据权利要求1-6中所述的方法，其中，所述确定性的函数关系为线性拟合函数，所述线性拟合函数表示为：
    D i＝kN i+c
    其中，D i为中子剂量率，单位为μSv/h；N i为入射中子与溴化镧晶体材料发生反应产生的特征γ能峰的净计数率，单位为cps；k，c为常数，且k>0。
  9. 一种中子剂量率仪，其中，所述中子剂量率仪具有溴化镧探测器，所述溴化镧探测器适于与入射中子发生反应产生特征γ能峰，并探测得到特征γ全能峰的能谱。
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