CN109669207B - Method for measuring neutron energy spectrum in neutron radiation field by utilizing lanthanum bromide detector - Google Patents
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- 238000000034 method Methods 0.000 title claims abstract description 51
- 238000001228 spectrum Methods 0.000 title claims abstract description 50
- XKUYOJZZLGFZTC-UHFFFAOYSA-K lanthanum(iii) bromide Chemical compound Br[La](Br)Br XKUYOJZZLGFZTC-UHFFFAOYSA-K 0.000 title claims abstract description 42
- 230000005855 radiation Effects 0.000 title claims abstract description 38
- 238000006243 chemical reaction Methods 0.000 claims abstract description 29
- 239000013078 crystal Substances 0.000 claims abstract description 21
- 238000001514 detection method Methods 0.000 claims abstract description 18
- 238000005316 response function Methods 0.000 claims abstract description 9
- 230000004044 response Effects 0.000 claims abstract description 7
- 238000005315 distribution function Methods 0.000 claims abstract description 4
- 238000005259 measurement Methods 0.000 claims description 17
- 238000000342 Monte Carlo simulation Methods 0.000 claims description 13
- 230000002452 interceptive effect Effects 0.000 claims description 6
- 238000011010 flushing procedure Methods 0.000 description 5
- 230000007613 environmental effect Effects 0.000 description 4
- 238000011160 research Methods 0.000 description 4
- 229910052695 Americium Inorganic materials 0.000 description 3
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical group [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 description 3
- 229910052790 beryllium Inorganic materials 0.000 description 3
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 3
- 229910052794 bromium Inorganic materials 0.000 description 3
- 229910052746 lanthanum Inorganic materials 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- WKBOTKDWSSQWDR-UHFFFAOYSA-N Bromine atom Chemical compound [Br] WKBOTKDWSSQWDR-UHFFFAOYSA-N 0.000 description 2
- GDTBXPJZTBHREO-UHFFFAOYSA-N bromine Substances BrBr GDTBXPJZTBHREO-UHFFFAOYSA-N 0.000 description 2
- 239000007795 chemical reaction product Substances 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000004927 fusion Effects 0.000 description 2
- FZLIPJUXYLNCLC-UHFFFAOYSA-N lanthanum atom Chemical compound [La] FZLIPJUXYLNCLC-UHFFFAOYSA-N 0.000 description 2
- 238000000691 measurement method Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 230000005658 nuclear physics Effects 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 238000002366 time-of-flight method Methods 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 238000004422 calculation algorithm Methods 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 230000009849 deactivation Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005281 excited state Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 238000001917 fluorescence detection Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 230000000155 isotopic effect Effects 0.000 description 1
- 239000004816 latex Substances 0.000 description 1
- 229920000126 latex Polymers 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
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- 238000001683 neutron diffraction Methods 0.000 description 1
- 238000009206 nuclear medicine Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 239000004065 semiconductor Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
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Abstract
The invention discloses a method for measuring neutron energy spectrum in a neutron radiation field by utilizing a lanthanum bromide detector, which comprises the following steps: (1) establishing an energy distribution function relation between neutron characteristic gamma energy peak net count and neutron fluence generated by inelastic scattering of neutrons and a detector:
φ(Ei) The neutron fluence of the ith energy group of the neutron spectrum to be detected;
is a neutron and79Br、81br and139the j characteristic gamma energy peak generated by inelastic scattering of La
A net count of;
for the j characteristic gamma energy peak generated in the detector pair
The intrinsic full energy peak detection efficiency;
is energy of EiThe neutron and the kth nuclide are reacted to generate a reaction section of a jth characteristic gamma energy peak;
the number of the nucleus which generates the jth reaction between the kth nuclide and the neutron in the crystal; pji(Ei) The probability of the ith energy group neutron participating in the jth reaction is shown; (2) aiming at the obtained j neutron characteristic gamma energy peaks, j response equations are established, and an equation set is formed; (3) determination of neutron characteristic gamma energy peak to neutron E of different energyiThe response function of (2); (4) and (5) resolving the equation set.
Description
Technical Field
The invention belongs to the technical field of radiation detection and environmental monitoring, and particularly relates to a method for measuring neutron energy spectrum in a neutron radiation field by using a lanthanum bromide detector.
Background
Neutron spectrum data is one of important parameters to be measured in nuclear physics basic research, reactor control, space particle detection, accelerator radiation field and radiation protection design, and is important content of neutron detection.
Neutron spectrum measurement methods are roughly divided into two major categories according to different neutron source types and application purposes: the method is characterized in that a single-energy neutron beam with specific energy is separated from a continuous energy spectrum neutron beam, the single-energy neutron beam is matched with a multi-channel time analyzer to obtain the energy distribution of neutron rays, and corresponding measuring methods comprise a neutron speed selector, a neutron diffraction spectrometer, a time-of-flight spectrometer and the like and are mainly used for neutron energy spectrum measurement of large nuclear physics experiment devices and reactors, wherein the time-of-flight method determines the neutron energy by measuring the time of the neutron flying through a certain selected distance, and is the most direct, classical and effective method for neutron energy spectrum measurement. And secondly, different signals are generated in the detector according to neutrons with different energies so as to obtain energy distribution information of incident neutron beams, and corresponding measurement methods comprise a proton nuclear back-flushing method, a nuclear reaction method, a multi-detector, a threshold detector and the like, and are mainly used for measurement of environmental radiation, an accelerator radiation field, reactor control, fusion neutron energy spectrum and the like. The proton nuclear back-flushing method is a well-developed method, and the developed detector comprises nuclear latex, a hydrogen-containing proportional counter tube, a planar membrane semiconductor, an organic scintillator, a telescope and the like. The nuclear back-flushing method determines an incident neutron energy spectrum by measuring the energy distribution of back-flushing nuclei emitted within a certain narrow angle range relative to the incident direction of a neutron beam, so that certain geometrical conditions are required, and the application of the nuclear back-flushing method in neutron energy spectrum measurement is limited to a certain extent. The nuclear reaction method measures the neutron energy spectrum through the total energy of the generated particles and is irrelevant to the incident direction of neutrons causing the reaction, so that the neutron beam does not need to be collimated in advance, the method is suitable for measuring the non-point source neutron energy spectrum, and is high in energy resolution ratio and suitableThe nuclear reaction has3H (n, d) T and6li (n, α) T. However, the spectrometer has high requirements on nuclear reaction conditions, and the required electronic circuit is complex, so that the spectrometer is mainly used for energy spectrum measurement in a laboratory. The multi-sphere spectrometer is the most common method for measuring neutron energy spectrum by a multi-detector, consists of a thermal neutron sensitive detector and a series of moderating body spherical shells with different thicknesses, has the characteristics of isotropy, wide energy response range, easiness in operation and the like, is widely used for measuring energy spectrum of a natural background, an accelerator radiation field and a laboratory constant-current neutron source, is mainly used in an environment with lower neutron flux level, and is commonly used in a radiation field with neutron energy lower than 20 MeV. The multi-sphere spectrometer is mature in technology, but the multi-sphere spectrometer has too many slowing spheres, takes time for measurement, is poor in portability and is inconvenient to use in conventional monitoring in the radiation protection field.
The lanthanum bromide detector is a new type inorganic scintillator detector developed in recent years, and its energy resolution ratio is high (<3 percent for 662keV gamma rays), high detection efficiency and good time resolution, is widely applied to gamma energy spectrum measurement, and obtains very good effect in the application research in the fields of nuclear resonance fluorescence detection, explosive detection, nuclear medicine imaging, environmental radiation monitoring, space radiation detection, fusion plasma and the like. The lanthanum bromide detector mainly comprises lanthanum bromide crystals, the constituent elements mainly comprise La and Br, and the natural isotopic abundance is considered to be that139La，79Br and81br, three nuclides are all stable nuclides. When neutrons are incident on the lanthanum bromide crystal material, the neutrons react with the crystal, specifically, with elastic scattering, inelastic scattering and radiation capture reactions of the three heavy nuclei. According to published nuclear databases, the probability of inelastic scattering increases rapidly with increasing energy, up to 2.5b, after neutron energies exceed a certain threshold. The products of the inelastic scattering reaction are neutrons with smaller energy and target nuclei with a certain kinetic energy. The target nuclei being in an excited state and emitting gamma rays when de-excited, e.g.79Br(n，n′γ)79mBr，79mBr deactivation emits gamma rays at 217 keV. The energies of these gamma rays are known and can be obtained from publicly published nuclear databases. In addition, neutron isRespectively with139La，79Br and81the reaction threshold and the reaction cross section of the Br at which inelastic scattering occurs can also be obtained from a nuclear database. Given the good response of the lanthanum bromide detector itself to gamma rays, these gamma rays are detected and resolved by the detector.
In recent years, with the development of research, foreign researchers find through experimental research that neutron energy spectrum measurement is realized by using a time-of-flight technology and a multichannel time analyzer on the basis of gamma rays generated by inelastic scattering of neutrons and a lanthanum bromide detector, and the detection efficiency of the neutron energy spectrum measurement on neutrons with 700keV can reach 5%. The detection efficiency of the single-slave detector is superior to that of other types of neutron detectors. However, the above detection method is based on the time-of-flight technique and is not applicable to the radiation protection field, wherein the acquisition of the sub-energy spectrum is based on the fact that the time required for neutrons with different energies to fly over a certain precise distance is different, and the time required for the neutrons to fly over a selected distance is converted into neutron energy by measuring the time-of-flight spectrum, so as to determine the neutron energy distribution. The method needs extremely precise distance control, accurately records the starting point time and the end point time of the neutron on the flight distance, needs other large-scale instruments, and obviously cannot be realized in the radiation protection field.
Disclosure of Invention
The present invention is directed to solving, at least to some extent, one of the technical problems in the related art. Therefore, one objective of the present invention is to provide a method for measuring neutron energy spectrum in neutron radiation field by using lanthanum bromide detector, which directly measures neutron energy spectrum in neutron radiation field by using a spectrum resolving algorithm through directly measuring characteristic gamma energy peak generated by inelastic scattering between neutron and lanthanum bromide detector.
In one aspect of the invention, a method for measuring neutron energy spectrum in a neutron radiation field by using a lanthanum bromide detector is provided. According to an embodiment of the invention, the method comprises:
(1) the functional relation equation between the neutron characteristic gamma energy peak net count generated by inelastic scattering of neutrons and lanthanum bromide crystals and the energy distribution of neutron fluence is established as shown in formula 1:
wherein phi (E)i) Neutron fluence, cm, for the ith energy group of the neutron spectrum to be measured-2；
Pji(Ei) The probability of the ith energy group neutron participating in the jth reaction is shown;
(2) aiming at j neutron characteristic gamma energy peaks obtained by measurement of a detector, j response equations are established and form an equation set:
(3) determining the characteristic gamma energy peak of each neutron to neutrons E with different energyiResponse function of
(4) The system of equations is solved as shown in equation 2 by the following interactive iterative method:
wherein,
for the radiation weight factor, it is calculated by the following formula:
juncertainty of the measured neutron characteristic gamma energy peak net count;
The method for measuring the neutron energy spectrum of the neutron radiation field by using the lanthanum bromide detector is based on a physical mechanism that incident neutrons can generate known energy de-excitation gamma rays through inelastic scattering with bromine nuclei and lanthanum nuclei, a functional relation equation between net counting of neutron characteristic gamma energy peaks and energy distribution of neutron fluence is established by using nuclear reaction products of lanthanum bromide and neutrons, and direct measurement of the neutron energy spectrum of the measured radiation field is realized by measuring the net counting of the neutron characteristic gamma energy peaks and adopting a spectrum resolving method of interactive iterative computation.
In addition, the method for measuring neutron energy spectrum in neutron radiation field by using the lanthanum bromide detector according to the above embodiment of the present invention may further have the following additional technical features:
in some embodiments of the present invention, in step (3), the jth characteristic gamma energy peak generated in the detector pair is calculated by a monte carlo simulation method
Intrinsic full energy peak detection efficiency of
Respectively calculating to obtain the crystal interior according to the density, volume, mass percentage of nuclide and natural abundance of isotope of lanthanum bromide crystal79Br、81Br and139number of nuclei of La
The energy obtained from the nuclear database is used as EiThe neutron and the kth nuclide react to generate a reaction cross section of a characteristic gamma energy peak of the jth neutron
Calculating the probability P of the i-th energy group neutron participating in the j-th reaction by a Monte Carlo simulation methodji(Ei)。
In some embodiments of the present invention, in step (3), the response function of each neutron characteristic gamma energy peak to monoenergetic neutrons with different energies is directly obtained by a monte carlo simulation method
Additional aspects and advantages of the invention will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the invention.
Drawings
The above and/or additional aspects and advantages of the present invention will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
FIG. 1 is a schematic flow chart of a method for measuring neutron energy spectrum in a neutron radiation field by using a lanthanum bromide detector according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of the basic structure of a lanthanum bromide detector;
FIG. 3 shows the environmental background spectrum and measurements obtained by the lanthanum bromide detector of the embodiment241An energy spectrum obtained by an Am-Be neutron source;
FIG. 4 is a drawing showing241The ISO standard spectrum of the Am-Be neutron source and the neutron energy spectrum of the neutron radiation field to Be detected obtained by the method of the embodiment.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are illustrative and intended to be illustrative of the invention and are not to be construed as limiting the invention.
In one aspect of the invention, a method for measuring neutron energy spectrum in a neutron radiation field by using a lanthanum bromide detector is provided. According to an embodiment of the invention, with reference to fig. 1, the method comprises:
s100: establishing a functional relation equation between neutron characteristic gamma energy peak net count and neutron fluence energy distribution generated by inelastic scattering of neutrons and lanthanum bromide crystals
In the step, specifically, a functional relation equation between the neutron characteristic gamma energy peak net count generated by inelastic scattering of neutrons and lanthanum bromide crystals and the energy distribution of neutron fluence is established as shown in formula 1:
wherein phi (E)i) Neutron fluence, cm, for the ith energy group of the neutron spectrum to be measured-2；
Pji(Ei) And calculating the probability of the ith energy group neutron participating in the jth reaction by a Monte Carlo simulation method.
S200: j response equations are established aiming at j neutron characteristic gamma energy peaks obtained by detector measurement, and an equation set is formed
In this step, the system of equations is composed of
S300: determining the characteristic gamma energy peak (j kinds in total) of each neutron to neutrons E with different energyiResponse function of
In the step, the j-th characteristic gamma energy peak generated in the detector pair is calculated and obtained by a Monte Carlo simulation method
Intrinsic full energy peak detection efficiency of
Respectively calculating to obtain the crystal interior according to the density, volume, mass percentage of nuclide and natural abundance of isotope of lanthanum bromide crystal79Br、81Br and139number of nuclei of La
The energy obtained from the nuclear database is used as EiThe neutron and the kth nuclide react to generate a reaction cross section of a characteristic gamma energy peak of the jth neutron
Calculating the probability P of the i-th energy group neutron participating in the j-th reaction by a Monte Carlo simulation methodji(Ei)。
In the step, the response of each neutron characteristic gamma energy peak to different energy monoenergetic neutrons is directly obtained by a Monte Carlo simulation methodResponse function
S400: equation set is resolved by the following interactive iterative method
In this step, the system of equations is solved by the following interactive iterative method as shown in formula 2:
wherein,
for the radiation weight factor, it is calculated by the following formula:
jfor measuring the uncertainty of the net count of the neutron characteristic gamma energy peak obtained, it is generally taken
The square root of (A), if
Is 0, thenjTaking 1;
The method for measuring the neutron energy spectrum of the neutron radiation field by using the lanthanum bromide detector is based on a physical mechanism that incident neutrons can generate known energy de-excitation gamma rays through inelastic scattering with bromine nuclei and lanthanum nuclei, a functional relation equation between net counting of neutron characteristic gamma energy peaks and energy distribution of neutron fluence is established by using nuclear reaction products of lanthanum bromide and neutrons, and direct measurement of the neutron energy spectrum of the measured radiation field is realized by measuring the net counting of the neutron characteristic gamma energy peaks and adopting a spectrum resolving method of interactive iterative computation.
The invention will now be described with reference to specific examples, which are intended to be illustrative only and not to be limiting in any way.
Examples
Using a 3in x 3in lanthanum bromide detector (LaBr)3Ce) with the basic composition structure as shown in figure 2; (ii) the neutron source is selected from americium beryllium neutron source241Am-Be neutron source).
The specific implementation process is as follows:
1) placing a lanthanum bromide detector at241The gamma energy spectrum obtained by measurement in the neutron radiation field formed by the Am-Be neutron source is shown in figure 3. Selecting neutrons and79Br、81br and139the net count of each gamma energy peak is calculated by adopting a Gaussian fitting and linear background method for 6 characteristic gamma energy peaks generated by inelastic scattering of La, and the net count is listed in Table 1. Characteristic gamma energy peaks resulting from inelastic scattering of an americium beryllium neutron source with lanthanum bromide crystals include, but are not limited to, the above energy values.
2) Respectively calculating the value of each parameter of the response function:
a) the intrinsic full-energy peak detection efficiency of the 3-inch lanthanum bromide detector for 6 characteristic gamma energy peaks generated in the detector is calculated by adopting a Monte Carlo simulation method and is listed in Table 1.
TABLE 13 InX 3in lanthanum bromide Detector detection efficiency for the characteristic gamma energy peak generated internally
b) Calculated according to the density, volume, mass percent of nuclide and natural abundance of isotope of the 3-inch lanthanum bromide crystalInto the crystal79Br、81Br and139number of nuclei of La.
c) Obtaining energy E from IAEA nuclear databaseiThe neutrons respectively react with the three nuclides to generate reaction cross sections of characteristic gamma energy peaks of 1-6 kinds of neutrons, and the probability that 100 groups of monoenergetic neutrons participate in the j reaction within a 0-10 MeV interval is calculated by adopting a Monte Carlo simulation method.
3) Based on the formula (1), response function equations of 6 3in x 3in lanthanum bromide detectors to an americium beryllium neutron source are established, and an equation set is formed.
4) Analyzing the equation set by adopting the methods of formulas (2) and (3), wherein the preset spectrum is241Standard spectra of Am-Be neutron sources. The result obtained by the analysis is shown in fig. 4, namely, the neutron energy spectrum of the neutron radiation field to be measured.
According to the actual measurement result in fig. 4, the energy distribution of the neutron fluence of the measured radiation field, i.e. the neutron energy spectrum, can be obtained by measuring the net count of the neutron characteristic gamma energy peak by using the response function relationship between the net count of the characteristic gamma energy peak generated by inelastic scattering of the neutron and the lanthanum bromide crystal and the neutron energy spectrum.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (3)
1. A method for measuring neutron energy spectrum in a neutron radiation field by utilizing a lanthanum bromide detector is characterized by comprising the following steps:
(1) the functional relation equation between the neutron characteristic gamma energy peak net count generated by inelastic scattering of neutrons and lanthanum bromide crystals and the energy distribution of neutron fluence is established as shown in formula 1:
wherein phi (E)i) Neutron fluence, cm, for the ith energy group of the neutron spectrum to be measured-2；
Pji(Ei) The probability of the ith energy group neutron participating in the jth reaction is shown;
(2) aiming at j neutron characteristic gamma energy peaks obtained by measurement of a detector, j response equations are established and form an equation set:
(3) determining the characteristic gamma energy peak of each neutron to neutrons E with different energyiResponse function of
(4) The system of equations is solved as shown in equation 2 by the following interactive iterative method:
wherein,
for the radiation weight factor, it is calculated by the following formula:
juncertainty of the measured neutron characteristic gamma energy peak net count;
2. The method of claim 1, wherein in step (3), the j-th characteristic gamma energy peak generated by the detector pair in the detector pair is calculated by a Monte Carlo simulation method
Intrinsic full energy peak detection efficiency of
Respectively calculating to obtain the crystal interior according to the density, volume, mass percentage of nuclide and natural abundance of isotope of lanthanum bromide crystal79Br、81Br and139number of nuclei of La
The energy obtained from the nuclear database is used as EiThe neutron and the kth nuclide react to generate a reaction cross section of a characteristic gamma energy peak of the jth neutron
Calculating the probability P of the i-th energy group neutron participating in the j-th reaction by a Monte Carlo simulation methodji(Ei)。
3. The method of claim 1, wherein in the step (3), the response function of each neutron characteristic gamma energy peak to different energy monoenergetic neutrons is directly obtained by a Monte Carlo simulation method
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