CN111487669A - Sleeve concentric multi-sphere neutron spectrometer, measuring method thereof and analysis processing system - Google Patents

Sleeve concentric multi-sphere neutron spectrometer, measuring method thereof and analysis processing system Download PDF

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CN111487669A
CN111487669A CN202010363869.8A CN202010363869A CN111487669A CN 111487669 A CN111487669 A CN 111487669A CN 202010363869 A CN202010363869 A CN 202010363869A CN 111487669 A CN111487669 A CN 111487669A
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neutron
sleeve
detector
energy
shells
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CN111487669B (en
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杨剑波
王昌铭
庹先国
成毅
王洪辉
李锐
彭颖
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Sichuan University of Science and Engineering
Chengdu Univeristy of Technology
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Chengdu Univeristy of Technology
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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/36Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/36Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
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Abstract

The invention relates to the field of neutron energy spectrum measurement, and particularly discloses a sleeve-shaft concentric multi-sphere neutron spectrometer, a measurement method and an analysis processing system thereof. The neutron spectrometer is provided with a sleeve shaft assembly and a concentric multi-ball shell on the sleeve shaft assembly, the drive assembly is arranged to carry out independent automatic drive on a ball shell on each sleeve shaft, polyethylene of different thicknesses can be quickly formed by switching and matching polyethylene ball shells of different thicknesses, measurement of energy of different neutrons is achieved, sensitivity of neutrons over 10MeV is improved, energy spectrum measurement of neutrons between 0 and 1000MeV is achieved, the same detector is used for measurement, and complexity of installation of a traditional multi-ball system is reduced. According to the measuring method, the pulse signals provided by the detector are converted into the corresponding counting value matrixes, and then the neutron energy spectrums corresponding to the counting value matrixes can be rapidly obtained by combining the calculation formula of the neutron energy spectrums and the response function matrixes simulated in advance, so that the measuring accuracy and stability are guaranteed.

Description

Sleeve concentric multi-sphere neutron spectrometer, measuring method thereof and analysis processing system
Technical Field
The invention relates to the field of neutron energy spectrum measurement, in particular to a sleeve-shaft concentric multi-sphere neutron spectrometer, a measurement method and an analysis processing system thereof.
Background
In recent years, accelerator technology has been developed and is widely used in life, especially in heavy ion therapy for cancer and clean energy. The ambient neutron dose equivalent generated by the accelerator can confirm whether the operation of the equipment meets the requirements or not, and the ambient neutron dose equivalent in the space can also be used as the effective dose equivalent received by a human body. And the accurate measurement of the neutron dose equivalent in the workplaces such as military and civil nuclear facilities, nuclear power stations and the like can better protect the health of personnel.
A multisphere neutron spectrometer system is originally proposed by Bonner et al in 1960 and is still widely used up to now, and a neutron detector is matched with polyethylene moderated spherical shells with different thicknesses to sequentially measure. The spherical thermal neutron detector arranged in the polyethylene moderating spherical shell is3He proportional counter, BF can also be used3Proportional counter and6l i.
The multisphere neutron spectrometer has the advantages of wide measurement range, isotropy, convenience in measurement and the like, so that the multisphere neutron spectrometer is widely used for measuring neutron energy spectrum. The multisphere neutron system mainly aims at neutron energy spectrum measurement in an internal energy region of more than 20MeV, and has lower sensitivity to high-energy neutrons of more than 20 MeV. The traditional multi-ball is matched and used by a plurality of independent ball shells, the work is complicated in the aspects of storage and transportation, and the conversion and use of the ball shells with different thicknesses are complex and time-consuming.
Disclosure of Invention
The invention provides a sleeve concentric multi-sphere neutron spectrometer, a measuring method and an analysis processing system thereof, and solves the technical problems that: the neutron more than 20MeV can not be detected to traditional multisphere neutron spectrometer to adopt a plurality of independent spherical shell collocation uses, switch complicacy, consuming time, and work is heavy and complicated in the aspect of accomodating, carrying.
In order to solve the technical problem, the invention provides a sleeve shaft concentric multi-ball neutron spectrometer which comprises a base, a main shaft arranged on the base, a sleeve shaft assembly nested on the main shaft, a concentric multi-ball shell nested on the sleeve shaft assembly, and a driving assembly connected with the sleeve shaft assembly; a detector is arranged on the main shaft; the concentric multi-ball shell comprises at least two layers of first ball shells and at least one layer of second ball shells, wherein the first ball shells are different in thickness, each layer of first ball shells is formed by combining a hemispherical porous metal shell and a hemispherical non-metal shell, the mass of the hemispherical porous metal shells is the same as that of the first ball shells, and the second ball shells are metal ball shells different from that of the hemispherical porous metal shells.
The sleeve shaft concentric multi-sphere neutron spectrometer provided by the invention is provided with a sleeve shaft assembly and a concentric multi-sphere shell sleeved on the sleeve shaft assembly (each layer of sphere shell consists of a hemispherical porous metal shell and a hemispherical non-metal shell which have the same mass), and a driving assembly is arranged to carry out independent automatic driving on the sphere shell on each sleeve shaft, and by means of converting and matching polyethylene sphere shells with different thicknesses, moderated layer polyethylenes with different thicknesses can be rapidly formed, so that measurement of different neutron energies is realized, the sensitivity of neutrons over 10MeV is improved, neutrons over 20MeV can be detected, the energy spectrum measurement of neutrons in a 0-1000MeV interval is realized, and an important basis is provided for further obtaining neutron dose; and the same detector is used for measurement, so that the complexity of the installation of the traditional multi-ball system is reduced.
In further embodiments, the detector is a neutron detector or a gamma ray detector.
The scheme further limits the detector to be a neutron detector or a gamma-ray detector, and can directly measure the neutron count value based on the neutron detector or the gamma-ray detector, so that the corresponding neutron energy spectrum can be conveniently obtained.
In a further embodiment, the main shaft comprises a left half shaft and a right half shaft having different diameters, and the detector is disposed at a central position of the main shaft.
The structure of main shaft is further injectd to this scheme, including left semi-axis and right semi-axis, left semi-axis sets firmly in base one side, and the concentric multi-ball shell that locates on it is rotatory as the axle spare mainly used confession cover, and right semi-axis installation is at the base opposite side, is used for installing the sleeve subassembly as the axle spare to thereby further supply the sleeve subassembly rotation of locating on it to drive concentric multi-ball shell rotatory.
In a further embodiment, the sleeve shaft assembly comprises a plurality of layers of sleeve shafts nested on the right half shaft from inside to outside, each layer of the sleeve shafts corresponds to one layer of the first spherical shell, the tail end of each layer of the sleeve shafts is connected with the driving assembly, the driving assembly independently drives each layer of the sleeve shafts to rotate, so that the rotation of the first spherical shell sleeved on the corresponding sleeve shaft is controlled, and 2 is matchednThe seed thickness is used for neutron measurement of the detector, and n is the number of layers of the hemispherical non-metal shell.
This scheme further inject the structure of sleeve axle subassembly, and the sleeve axle subassembly sets up the sleeve axle that corresponds the level according to the number of piles of first spherical shell to with the end link drive assembly of sleeve axle, the sleeve axle acquires the power of revolving that drive assembly acts on each first spherical shell and drives corresponding first spherical shell and rotate, thereby realizes 2nThe thickness combination of the hemispherical non-metal shell is used for measuring neutron count values corresponding to the thickness combination by the detector.
In a further embodiment, each layer of the sleeve shaft is provided with a chain wheel, and the driving assembly comprises a chain set linked with the chain wheel, a motor set driving the chain set, and a controller controlling the motor set.
This scheme further inject the sleeve shaft and pass through the chain group connection of sprocket and drive assembly, and both cooperate each other and can realize driving the first spherical shell that corresponds rotatory. This scheme has still injectd drive assembly and has still included motor unit and control motor unit's controller to realize controlling each motor of motor unit through the controller and controlling the first spherical shell that corresponds and rotate preset angle (180 degrees mainly), thereby realize 2nThickness combination of semispherical nonmetallic shell for detector measurement pairNeutron count value combined with thickness.
The invention also provides a measuring method of the sleeve concentric multi-sphere neutron spectrometer, which can be applied to the sleeve concentric multi-sphere neutron spectrometer and comprises the following steps:
by rotating the different first spherical shells by 180 degrees, 2 is simulated in a common modenPlanting the combined thickness of the hemispherical non-metal shell, and obtaining a response function matrix under the combined thickness, wherein n is the number of layers of the hemispherical non-metal shell;
by rotating the different first spherical shells by 180 degrees, 2 is simulated in a common modenThe combined thickness of the hemispherical non-metal shell is measured by a detector, and a count value matrix under each combined thickness is obtained;
and importing the counting value matrix into the corresponding response function matrix to obtain the corresponding neutron energy spectrum.
The measuring method of the sleeve-shaft concentric multi-sphere neutron spectrometer can be used for the sleeve-shaft concentric multi-sphere neutron spectrometer (or other sleeve-shaft concentric multi-sphere neutron spectrometers), pulse signals provided by a detector are converted into corresponding count value matrixes, neutron energy spectrums corresponding to the count value matrixes can be rapidly obtained by combining a calculation formula of the neutron energy spectrums and response function matrixes simulated in advance, and the measuring accuracy and stability are guaranteed.
In a further embodiment, the obtaining a response function matrix at the combined thickness specifically includes:
according to the discrete value of j different energy group energy values under the neutron energy of thermal neutron-1000 MeV obtained by simulation to 2nA response function reference matrix at the combined thickness, the response function matrix formed by:
Figure BDA0002475923530000031
wherein R is11-RijFor the energy response of the detector to neutrons or gamma rays, i-2nAnd j represents different energy groups.
According to the scheme, response functions under different combination thicknesses are listed in a matrix mode, the energy response of each combination thickness is displayed, and later-stage calculation is facilitated.
In a further embodiment, the matrix of count values is:
Figure BDA0002475923530000041
wherein N is1-N32Respectively, a count value generated from the detector for the measurement signal at each of the combined thicknesses.
The technical values actually measured by the detectors under different combined thicknesses are listed in a matrix mode, so that later-stage calculation is facilitated.
In a further embodiment, the introducing the count matrix into the corresponding response function matrix to obtain a corresponding neutron spectrum specifically includes:
1) calculating a neutron energy spectrum according to the formula:
Figure BDA0002475923530000042
discretizing to obtain:
Figure BDA0002475923530000043
where φ (E) is the neutron spectrum sought, Rφ(E) For the energy response function of simulated neutrons or gamma rays, E characterizing the neutron energy, dEIs the differential of E;
2) substituting equations (1) and (2) into equation (4) yields equation (5):
Figure BDA0002475923530000044
to obtain
Figure BDA0002475923530000045
The neutron energy corresponding to each count value in the solved neutron energy spectrum is obtained;
3) neutron energy to be solved
Figure BDA0002475923530000046
Converted into corresponding neutron energy spectra.
The scheme directly provides a calculation formula of the neutron energy spectrum, the calculation formula is substituted into a known simulated response function matrix and a known count value matrix, the neutron energy matrix can be obtained, the neutron energy spectrum can be directly output by adopting automatic software according to the neutron energy matrix, and therefore the final output of the neutron energy spectrum is achieved.
The invention also provides an analysis processing system of the sleeve-shaft concentric multi-sphere neutron spectrometer, which comprises a signal collecting unit, a data processing unit and a display unit which are sequentially connected;
the signal collection unit is used for connecting a detector of the sleeve shaft concentric multi-sphere neutron spectrometer to obtain a pulse signal output by the detector;
the data processing unit is used for converting the acquired pulse signals into corresponding count value matrixes and then executing the measuring method to obtain corresponding neutron energy spectrums;
the display unit is used for displaying the neutron energy spectrum.
The analysis processing system of the sleeve concentric multi-sphere neutron spectrometer can be used for the sleeve concentric multi-sphere neutron spectrometer (or other sleeve concentric multi-sphere neutron spectrometers), the signal acquisition unit is adopted to acquire the pulse signal of the detector, the pulse signal is further input into the data processing unit, the data processing unit processes the pulse signal according to a preset measurement method (the measurement method of the sleeve concentric multi-sphere neutron spectrometer or other measurement methods can be adopted), a corresponding neutron energy spectrum is acquired, and then the neutron energy spectrum is displayed by the display unit, so that the work of signal acquisition, data processing, result display and the like in one system is realized, the measurement consistency is ensured, and the error problem caused by the adoption of a plurality of signal acquisition systems and data processing systems in the prior art is avoided.
Drawings
Fig. 1 is a schematic structural diagram (lower half vertical half section) of a quill concentric multi-sphere neutron spectrometer provided in embodiment 1 of the present invention;
fig. 2 is a schematic structural diagram of the base in fig. 1 according to embodiment 1 of the present invention;
fig. 3 is a schematic structural diagram of the spindle in fig. 1 according to embodiment 1 of the present invention;
FIG. 4 is a vertical cross-sectional view of the quill assembly of FIG. 1 provided in embodiment 1 of the present invention;
FIG. 5 is a vertical sectional view of the lower half of the concentric multi-ball housing of FIG. 1 according to embodiment 1 of the present invention;
fig. 6 is a vertical sectional view of the driving assembly of fig. 1 provided in embodiment 1 of the present invention;
fig. 7 is a flowchart illustrating steps of a method for measuring a sleeve-axis concentric multi-sphere neutron spectrometer according to embodiment 2 of the present invention;
fig. 8 is a block diagram of an analysis processing system of a sleeve-axis concentric multi-sphere neutron spectrometer according to embodiment 3 of the present invention.
Detailed description of the preferred embodiments
The following is illustrated in further detail by specific embodiments:
reference numerals in the drawings of the specification include: the device comprises a concentric multi-ball shell A, a sleeve shaft component B, a driving component C, a base 1, a main shaft 2, sleeve shafts 3-7, a detector 8, a screw 9, a hemispherical polyethylene shell 10-15, a metal lead ball shell 13, a hemispherical porous stainless steel shell 16-20, a chain group 21, a motor group 22, a controller 23, an analysis processing system 30, a signal collection unit 301, a data processing unit 302 and a display unit 303.
Example 1
In order to solve the technical problems that the traditional multi-ball neutron spectrometer cannot detect neutrons of more than 20MeV, adopts a plurality of independent ball shells to be matched for use, is complex to switch and consumes time, and is complicated to work in the aspects of storage and transportation, the invention provides a sleeve shaft concentric multi-ball neutron spectrometer which at least comprises a base, a main shaft arranged on the base, a sleeve shaft assembly nested on the main shaft, a concentric multi-ball shell nested on the sleeve shaft assembly, and a driving assembly connected with the sleeve shaft assembly; a detector is arranged on the main shaft; the concentric multi-ball shell comprises at least two layers of first ball shells and at least one layer of second ball shells, wherein the first ball shells are different in thickness, each layer of first ball shells is formed by combining a hemispherical porous metal shell and a hemispherical non-metal shell, the mass of the hemispherical porous metal shells is the same as that of the first ball shells, and the second ball shells are metal ball shells different from that of the hemispherical porous metal shells.
The detector is a neutron detector or a gamma-ray detector, and outputs corresponding pulse signals during measurement. The neutron counting value can be directly measured based on the neutron detector or the gamma-ray detector, and the corresponding neutron energy spectrum can be conveniently obtained.
As a preferred embodiment, taking a concentric multi-sphere housing a as an example of a six-layer spherical shell, as shown in fig. 1, a quill concentric multi-sphere neutron spectrometer provided by an example of the present invention includes a base 1, a main shaft 2, five layers of quill 3-7 (quill assembly B), a concentric multi-sphere housing a formed by combining five layers of hemispherical polyethylene housings 10, 11, 12, 14, 15 (hemispherical non-metal housings) and five layers of hemispherical porous stainless steel housings 16-20 (hemispherical porous metal housings), a metal lead spherical shell 13 (metal spherical shell) disposed between the hemispherical polyethylene housings 12, 14, and a driving assembly C formed by a chain set 21, a motor set 22 and a controller 23.
Further, as shown in fig. 2, the base 1 is a rectangular plate, four supporting legs are arranged at four corners of the lower portion of the plate, two supporting rectangular plates are symmetrically distributed on the plate, a semicircular notch (for example, with a diameter of 7.6 cm) is formed in the center of the upper end of the left supporting plate, and a semicircular notch (for example, with a diameter of 4.48 cm) is formed in the corresponding position of the right supporting plate.
As shown in fig. 3, the main shaft 2 includes a left half shaft (a steel pipe with a diameter of 7.6cm and a wall thickness of 3 mm) and a right half shaft (a solid steel rod with a diameter of 1.7 cm) with different diameters, and is respectively embedded in a semicircular notch on a left support plate and a semicircular notch on a right support plate on the base 1. The left half shaft and the right half shaft are connected by four arc steel bars which are symmetrically distributed in a welding way, and the detector 8 is arranged at the center of the arc steel bars. The left half shaft is embedded in a semicircular notch on one side of the base 1 and is mainly used for rotating the concentric multi-ball shell A sleeved on the left half shaft as a shaft, and the right half shaft is embedded in a semicircular notch on the other side of the base 1 and is used for installing a sleeve shaft assembly B as a shaft so as to further drive the concentric multi-ball shell A to rotate by the sleeve shaft assembly B sleeved on the right half shaft.
As shown in fig. 4, the sleeve shaft assembly B includes 5 sleeve shafts 7, 6, 5, 4, 3 (hollow steel pipes) with different sizes, which are sleeved on the right half shaft of the main shaft 2 from inside to outside, two convex blocks matched with the spherical shell are symmetrically welded on the outer wall of the left end of each sleeve shaft, and a circular chain wheel is welded on the right end. The sleeve shafts 7, 6, 5, 4 and 3 acquire the rotary force of the driving component C acting on each first spherical shell to drive the corresponding first spherical shell to rotate, thereby realizing 2nThe combination of thicknesses of the hemispherical polyethylene shells 10, 11, 12, 14, 15 is used for the detector 8 to measure the neutron count value of the corresponding combination of thicknesses.
As shown in fig. 5, the concentric multi-sphere shell a includes hemispherical polyethylene shells 10, 11, 12, 14, 15 nested inside to outside on the sleeve shaft assembly (surrounding the detector 6), and the hemispherical polyethylene shells 10, 11, 12, 14, 15 are connected with hemispherical porous stainless steel shells 16, 17, 18, 19, 20 in sequence through screws 9 to form a complete spherical shell (first spherical shell). Between the hemispherical polyethylene shells 12, 14 is a metallic lead spherical shell 13 (the second complete spherical shell). The left end of each layer of complete spherical shell is provided with a round hole with the diameter of 7.6cm, and the right end is provided with holes with the shapes which are respectively corresponding to the convex blocks of the sleeve shafts 3, 4, 5, 6 and 7.
As shown in fig. 6, the driving assembly C includes a chain set 21 linked with the chain wheel, a motor set 22 (including 5 sets of stepping motors) for driving the chain set 21, and a controller 23 for controlling the motor set 22, wherein the chain set has 5 chains, and the chain set connects the gear on each sleeve shaft and one stepping motor in the motor set 22. The embodiment further defines that the sleeve shafts 7, 6, 5, 4 and 3 are connected with the chain set 21 of the driving component C through chain wheels, and the two are mutually matched to drive the corresponding first spherical shell to rotate. The embodiment further defines that the driving assembly C further includes a motor unit 22 and a controller 23 for controlling the motor unit 22, so as to control each motor of the motor unit 22 to rotate the corresponding first spherical shell by a preset angle (mainly 180 °) by controlling each motor of the motor unit 22 through the controller 23, thereby implementing 2nHemispherical polyethyleneThe thickness combinations of the shells 10, 11, 12, 14, 15 are used for the detector 8 to measure the neutron count values of the corresponding thickness combinations. It is known that how the controller 23 controls the operation of the stepping motor, and the description of the embodiment is omitted. In other embodiments, the driving assembly C may have other structures as long as it can drive the circular sprocket on the sleeve shaft to rotate by a preset angle.
It should be noted that the thicknesses of the hemispherical polyethylene shells 10, 11, 12, 14, 15 with different thicknesses can be determined according to actual measurement requirements, for example, 1, 2, 4, 8, 16cm (arranged in an equal ratio array), and the mass of the hemispherical porous stainless steel shells 16, 17, 18, 19, 20 connected with the hemispherical porous stainless steel shells is equal to that of the corresponding hemispherical polyethylene shells. The controller 23 controls the motor unit 22 to rotate the corresponding sleeve shaft, and the matching of the semi-spherical polyethylene shell and the semi-spherical porous stainless steel shell can be converted to form a component 25The polyethylene spherical shell with 32 thicknesses can meet the basic measurement requirement. The thickness of the lead spherical shell 13 is 1 cm.
The sleeve shaft concentric multi-ball neutron spectrometer provided by the embodiment of the invention is provided with a sleeve shaft component B comprising a plurality of layers of sleeve shafts, a concentric multi-ball shell A (each layer of ball shell consists of a hemispherical porous metal shell and a hemispherical non-metal shell which have the same mass) sleeved on the sleeve shaft component, and a driving component C for carrying out independent automatic driving on the ball shell on each sleeve shaft, and by converting and matching polyethylene ball shells with different thicknesses, moderated layer polyethylenes with different thicknesses can be rapidly formed, so that the measurement of energy of different neutrons is realized, neutrons above 20MeV can be detected, the measurement of neutron energy spectrum in the interval of 0-1000MeV is realized, and an important basis is provided for further obtaining neutron dose; and the same probe 8 is used for measurement, the complexity of the installation of the traditional multi-ball system is reduced.
Example 2
Referring to fig. 7, this embodiment provides a method for measuring a sleeve concentric multi-sphere neutron spectrometer, which can be applied to the sleeve concentric multi-sphere neutron spectrometer described in embodiment 1, taking an example that a hemispherical non-metal shell is a hemispherical polyethylene shell and is provided with 5 layers (n is 5), and the method specifically includes the steps of:
s1, simulating 2 in a common mode by rotating 180 degrees of different first spherical shellsnAnd (3) planting the combined thickness of the hemispherical non-metal shell, and obtaining a response function matrix under the combined thickness, wherein n is the number of layers of the hemispherical non-metal shell.
In this step, the obtaining a response function matrix under the combined thickness specifically includes:
according to the discrete value of j different energy group energy values under the neutron energy of thermal neutron-1000 MeV obtained by simulation to 2nA response function reference matrix at the combined thickness, the response function matrix formed by:
Figure BDA0002475923530000081
wherein R is11-RijFor the energy response of the detector to neutrons or gamma rays, i-2nAnd j represents different energy groups.
In the step, response functions under different combined thicknesses are listed in a matrix mode, the energy response of each combined thickness is shown, and later-stage calculation is facilitated.
S2, simulating 2 in a common mode by rotating the first spherical shells at different angles by 180 degreesnThe combined thickness of the hemispherical non-metallic shells is measured by a detector to obtain a matrix of count values at each of the combined thicknesses.
In step S2, the count value matrix is specifically:
Figure BDA0002475923530000091
wherein N is1-N32Respectively, a count value generated from the detector for the measurement signal at each of the combined thicknesses.
Obtaining N1-N32The process comprises the following steps:
① 180 rotating sleeve shaft 7 by 180 degrees, measuring environmental neutrons for the 1 st time, and outputting pulse by detector 8Converting the pulse signal into a digital signal, and calculating the count value N of the obtained digital signal1
② the sleeve shaft 7 is restored to the initial position, the sleeve shaft 6 is rotated by 180 degrees, the 2 nd measurement is carried out to the environmental neutrons, the pulse signal is output, the signal acquisition unit converts the pulse signal into a digital signal, and the count value N of the obtained digital signal is obtained2
……
By analogy, each hemispherical non-metal shell may contribute two state values, "with" (taking part in measurement) and "without" (not taking part in measurement), and the combined thickness should have 2 × 2 ═ 2532 kinds.
In the step, the technical values actually measured by the detectors under different combined thicknesses are listed in a matrix mode, so that later-stage calculation is facilitated.
And S3, importing the counting value matrix into the corresponding response function matrix to obtain the corresponding neutron energy spectrum.
The step S3 specifically includes:
1) calculating a neutron energy spectrum according to the formula:
Figure BDA0002475923530000092
discretizing to obtain:
Figure BDA0002475923530000093
where φ (E) is the neutron spectrum sought, Rφ(E) For the energy response function of simulated neutrons or gamma rays, E characterizing the neutron energy, dEIs the differential of E;
2) substituting equations (1) and (2) into equation (4) yields equation (5):
Figure BDA0002475923530000101
to obtain
Figure BDA0002475923530000102
Is in solutionNeutron energy corresponding to each count value in the sub-energy spectrum;
3) neutron energy to be solved
Figure BDA0002475923530000103
Converted into corresponding neutron energy spectra.
The step directly provides a calculation formula of the neutron energy spectrum, the neutron energy matrix can be obtained by substituting the known simulated response function matrix and the known simulated count value matrix, and the neutron energy spectrum can be directly output by adopting automatic software according to the neutron energy matrix, so that the final output of the neutron energy spectrum is realized.
The measurement method of the sleeve concentric multi-sphere neutron spectrometer provided by the embodiment 2 of the invention can be used for the sleeve concentric multi-sphere neutron spectrometer (or other sleeve concentric multi-sphere neutron spectrometers) described in the embodiment 1, the pulse signal provided by the detector 8 is converted into a corresponding count value matrix, and then the neutron energy spectrum corresponding to the count value matrix can be rapidly obtained by combining a calculation formula of the neutron energy spectrum and a response function matrix simulated in advance, so that the measurement accuracy and stability are ensured.
Example 3
Embodiment 3 of the present invention further provides an analysis processing system 30 for a sleeve-axis concentric multi-sphere neutron spectrometer, which can be applied to the sleeve-axis concentric multi-sphere neutron spectrometer described in embodiment 1, as shown in fig. 8, and includes a signal collection unit 301, a data processing unit 302, and a display unit 303, which are sequentially connected.
The signal collection unit 301 is used for connecting the detector 8 of the sleeve-axis concentric multi-sphere neutron spectrometer to obtain a pulse signal output by the detector 8. The signal collection unit 301 can adopt a data transmission line and is connected between the signal output end of the detector 8 and the signal input end of the data processing unit 302; or, a wireless network communication module is adopted to interact with the wireless network communication module of the detector 8, so that the corresponding pulse signal can be obtained.
The data processing unit 302 is configured to convert the acquired pulse signals into a corresponding count value matrix, and then execute the measurement method of the sleeve-axis concentric multi-sphere neutron spectrometer described in embodiment 2 to obtain a corresponding neutron energy spectrum. Most of the data processing unit 302 is an MCU processor, and the specific calculation can be implemented by software loaded on the MCU processor, more specifically, by writing a calculation program (the measurement method described in the above embodiment 2) by software, so that the corresponding neutron spectrum can be directly calculated after the pulse signal of the signal collecting unit 301 is obtained.
The display unit 303 is configured to display the neutron energy spectrum, and can be implemented by using a display.
In practical applications, the analysis processing system 30 is integrated in one computer (integrated with various signal input ports, processing motherboard and display), and a single device is provided for each unit or only two units are integrated in one device, so that information interaction between the devices is performed, which is also an embodiment and is within the protection scope of the present invention.
The analysis processing system 30 of the sleeve-axis concentric multi-sphere neutron spectrometer provided in embodiment 3 of the present invention is used for the sleeve-axis concentric multi-sphere neutron spectrometer (or other sleeve-axis concentric multi-sphere neutron spectrometers) in embodiment 1, the signal acquisition unit 301 is used to acquire the pulse signal of the detector 8, and the pulse signal is further input to the data processing unit 302, and the data processing unit 302 processes the pulse signal according to a preset measurement method (which may be the measurement method of the sleeve-axis concentric multi-sphere neutron spectrometer described in embodiment 2 or other measurement methods), so as to acquire a corresponding neutron energy spectrum, and then displays the neutron energy spectrum by the display unit 303, thereby realizing the work of signal acquisition, data processing, result display, and the like in one system, thereby ensuring the measurement consistency and avoiding the error problem caused by the existing adoption of multiple signal acquisition systems and data processing systems.
The foregoing are merely exemplary embodiments of the present invention, and no attempt is made to show structural details of the invention in more detail than is necessary for the fundamental understanding of the art, the description taken with the drawings making apparent to those skilled in the art how the several forms of the invention may be embodied in practice with the teachings of the invention. It should be noted that, for those skilled in the art, without departing from the structure of the present invention, several changes and modifications can be made, which should also be regarded as the protection scope of the present invention, and these will not affect the effect of the implementation of the present invention and the practicability of the patent. The scope of the claims of the present application shall be determined by the content of the claims, and the description of the specific embodiments and the like in the specification shall be used to explain the content of the claims.

Claims (10)

1. The utility model provides a concentric multisphere neutron spectrometer of sleeve axle which characterized in that: the device comprises a base, a main shaft arranged on the base, a sleeve shaft assembly nested on the main shaft, a concentric multi-ball shell sleeved on the sleeve shaft assembly, and a driving assembly connected with the sleeve shaft assembly; a detector is arranged on the main shaft; the concentric multi-ball shell comprises at least two layers of first ball shells and at least one layer of second ball shells, wherein the first ball shells are different in thickness, each layer of first ball shells is formed by combining a hemispherical porous metal shell and a hemispherical non-metal shell, the mass of the hemispherical porous metal shells is the same as that of the first ball shells, and the second ball shells are metal ball shells different from that of the hemispherical porous metal shells.
2. The quill concentric multisphere neutron spectrometer of claim 1, wherein: the detector is a neutron detector or a gamma ray detector.
3. The quill concentric multisphere neutron spectrometer of claim 1, wherein: the main shaft comprises a left half shaft and a right half shaft which have different diameters, and the detector is arranged in the center of the main shaft.
4. A quill concentric multisphere neutron spectrometer as in claim 3, wherein: the sleeve shaft assembly comprises a plurality of layers of sleeve shafts which are nested on the right half shaft from inside to outside, and each layer of sleeve shaft corresponds to one layer of sleeve shaftThe tail end of each layer of sleeve shaft is connected with the driving component, and the driving component independently drives each layer of sleeve shaft to rotate, so that the first spherical shell sleeved on the corresponding sleeve shaft is controlled to rotate, and 2 is matchednThe seed thickness is used for neutron measurement of the detector, and n is the number of layers of the hemispherical non-metal shell.
5. The quill concentric multisphere neutron spectrometer of claim 4, wherein: each layer the sleeve shaft is provided with a chain wheel, and the driving component comprises a chain group linked with the chain wheel, a motor unit driving the chain group, and a controller controlling the motor unit.
6. A measurement method of a sleeve-axis concentric multi-sphere neutron spectrometer is applied to the sleeve-axis concentric multi-sphere neutron spectrometer of any one of claims 1 to 5, and is characterized by comprising the following steps:
by rotating the different first spherical shells by 180 degrees, 2 is simulated in a common modenPlanting the combined thickness of the hemispherical non-metal shell, and obtaining a response function matrix under the combined thickness, wherein n is the number of layers of the hemispherical non-metal shell;
by rotating the different first spherical shells by 180 degrees, 2 is simulated in a common modenThe combined thickness of the hemispherical non-metal shell is measured by a detector, and a count value matrix under each combined thickness is obtained;
and importing the counting value matrix into the corresponding response function matrix to obtain the corresponding neutron energy spectrum.
7. The method according to claim 6, wherein the obtaining of the response function matrix at the combined thickness specifically comprises:
according to the discrete value of j different energy group energy values under the neutron energy of thermal neutron-1000 MeV obtained by simulation to 2nA response function reference matrix at the combined thickness, the response function matrix formed by:
Figure FDA0002475923520000021
wherein R is11-RijFor the energy response of the detector to neutrons or gamma rays, i-2nAnd j represents different energy groups.
8. The method of claim 7, wherein the matrix of count values is:
Figure FDA0002475923520000022
wherein N is1-N32Respectively, a count value generated from the detector for the measurement signal at each of the combined thicknesses.
9. The method according to claim 8, wherein the step of introducing the matrix of count values into the corresponding matrix of response functions to obtain the corresponding neutron spectrum comprises:
1) calculating a neutron energy spectrum according to the formula:
Figure FDA0002475923520000023
discretizing to obtain:
Figure FDA0002475923520000024
where φ (E) is the neutron spectrum sought, Rφ(E) For the energy response function of simulated neutrons or gamma rays, E characterizing the neutron energy, dEIs the differential of E;
2) substituting equations (1) and (2) into equation (4) yields equation (5):
Figure FDA0002475923520000025
to obtain
Figure FDA0002475923520000031
The neutron energy corresponding to each count value in the solved neutron energy spectrum is obtained;
3) neutron energy to be solved
Figure FDA0002475923520000032
Converted into corresponding neutron energy spectra.
10. The utility model provides an analytic processing system of concentric multisphere neutron spectrometer of cover axle which characterized in that: comprises a signal collection unit, a data processing unit and a display unit which are connected in sequence;
the signal collection unit is used for connecting a detector of the sleeve shaft concentric multi-sphere neutron spectrometer to obtain a pulse signal output by the detector;
the data processing unit is used for converting the acquired pulse signals into a corresponding count value matrix and then executing the measuring method according to any one of claims 6 to 9 to obtain a corresponding neutron energy spectrum;
the display unit is used for displaying the neutron energy spectrum.
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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114035222A (en) * 2021-10-28 2022-02-11 中国船舶重工集团公司第七一九研究所 Online neutron energy spectrum measuring device
CN114047541A (en) * 2021-11-10 2022-02-15 中国原子能科学研究院 Multi-sphere spectrometer for neutron energy spectrum measurement

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4217496A (en) * 1978-03-14 1980-08-12 The United States Of America As Represented By The Secretary Of Health, Education And Welfare Portable instrument for measuring neutron energy spectra and neutron dose in a mixed n-γ field
WO2013066882A1 (en) * 2011-11-01 2013-05-10 Slaughter David M Neutron spectrometer
JP2014081209A (en) * 2012-10-12 2014-05-08 Hamamatsu Photonics Kk Neutron radiographic apparatus
CN204740350U (en) * 2015-01-26 2015-11-04 清华大学 Analysor of many balls neutron spectrometer and many balls neutron spectrometer
CN105785425A (en) * 2016-04-26 2016-07-20 成都理工大学 Water injection and drainage full-automatic multisphere neutron spectrometer and measurement method
CN106950593A (en) * 2017-03-30 2017-07-14 成都理工大学 Pumping water multilayer concentric ball device and neutron energy spectrum detection system
CN210376708U (en) * 2019-04-11 2020-04-21 成都理工大学 Neutron energy spectrum measuring system

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4217496A (en) * 1978-03-14 1980-08-12 The United States Of America As Represented By The Secretary Of Health, Education And Welfare Portable instrument for measuring neutron energy spectra and neutron dose in a mixed n-γ field
WO2013066882A1 (en) * 2011-11-01 2013-05-10 Slaughter David M Neutron spectrometer
JP2014081209A (en) * 2012-10-12 2014-05-08 Hamamatsu Photonics Kk Neutron radiographic apparatus
CN204740350U (en) * 2015-01-26 2015-11-04 清华大学 Analysor of many balls neutron spectrometer and many balls neutron spectrometer
CN105785425A (en) * 2016-04-26 2016-07-20 成都理工大学 Water injection and drainage full-automatic multisphere neutron spectrometer and measurement method
CN106950593A (en) * 2017-03-30 2017-07-14 成都理工大学 Pumping water multilayer concentric ball device and neutron energy spectrum detection system
CN210376708U (en) * 2019-04-11 2020-04-21 成都理工大学 Neutron energy spectrum measuring system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
HUAILIANG LI: "DOUBLE-EXPONENTIAL FITTING FUNCTION FOR EVALUATION OF COSMIC-RAY-INDUCED NEUTRON FLUENCE", 《RADIATION PROTECTION DOSIMETRY》 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114035222A (en) * 2021-10-28 2022-02-11 中国船舶重工集团公司第七一九研究所 Online neutron energy spectrum measuring device
CN114047541A (en) * 2021-11-10 2022-02-15 中国原子能科学研究院 Multi-sphere spectrometer for neutron energy spectrum measurement

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