CN113640854B - Nuclear recoil method gas detector energy scale method - Google Patents

Nuclear recoil method gas detector energy scale method Download PDF

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CN113640854B
CN113640854B CN202110873265.2A CN202110873265A CN113640854B CN 113640854 B CN113640854 B CN 113640854B CN 202110873265 A CN202110873265 A CN 202110873265A CN 113640854 B CN113640854 B CN 113640854B
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gas detector
uranium
peak value
energy
alpha
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CN113640854A (en
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李立华
莫玉俊
李玮
刘蕴韬
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China Institute of Atomic of Energy
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China Institute of Atomic of Energy
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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • G01T3/001Spectrometry
    • G01T3/003Recoil spectrometers
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • G01T3/008Measuring neutron radiation using an ionisation chamber filled with a gas, liquid or solid, e.g. frozen liquid, dielectric

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  • Spectroscopy & Molecular Physics (AREA)
  • Health & Medical Sciences (AREA)
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Abstract

The invention belongs to the technical field of neutron measurement, and particularly relates to an energy scale method of a nuclear recoil method gas detector. Step S1, obtaining the ratio of the number of uranium isotope atomic nuclei in uranium materials used for plating targets; s2, acquiring a first alpha spectrum, and confirming a channel address corresponding to a first counting peak value, wherein the first alpha spectrum refers to an alpha spectrum emitted by a uranium target in a gas detector, and the first counting peak value refers to a counting peak value in the first alpha spectrum; step S3, obtaining a second alpha spectrum, and confirming the energy corresponding to a second counting peak value, wherein the second alpha spectrum refers to a simulated alpha spectrum of uranium target emission in a simulated gas detector obtained through a simulation program, and the second counting peak value refers to a counting peak value in the second alpha spectrum; and S4, completing the energy scale of the gas detector through the channel address corresponding to the first counting peak value and the energy corresponding to the second counting peak value. The invention can complete the energy scale of the nuclear recoil method gas detector measuring system without generating monoenergetic neutrons by an accelerator.

Description

Nuclear recoil method gas detector energy scale method
Technical Field
The invention belongs to the technical field of neutron measurement, and particularly relates to an energy scale method of a nuclear recoil method gas detector.
Background
The nuclear recoil method is one of several main methods for neutron measurement, and is mainly used for fast neutron measurement, and the basic principle is that the collided nucleus obtains certain kinetic energy by utilizing the collision of neutrons and atomic nuclei, and the kinetic energy obtained by the collided nucleus is larger when the mass of the collided nucleus is smaller according to the law of conservation of momentum and kinetic energy, so that the hydrogen atomic nucleus is selected as the recoil nucleus to be the optimal choice, and the kinetic energy obtained by the hydrogen nuclear can be expressed as a formula (1):
E H=En·cos2 # -formula (1)
Wherein:
e H -represents the kinetic energy obtained by back flushing the hydrogen nuclei;
E n —represents the kinetic energy of the incident neutron;
θ—represents the angle between the direction of exit of the hydrogen nuclei and the direction of the incoming neutrons.
In principle, the desired neutron spectrum can be obtained from the measured proton spectrum by a spectrum decomposition method, and the primary condition is that the measured proton spectrum is subjected to energy graduation, and for a hydrogen-containing proportional counter or an ionization chamber, since the outer layer is generally made of stainless steel with the thickness of 1mm, it is obvious that the energy graduation by using an accelerator proton beam is not practical, a monoenergetic neutron generated by the accelerator can be adopted, and then the energy graduation is carried out by the energy of the recoil proton, but a laboratory capable of providing monoenergetic neutrons is very few.
Disclosure of Invention
The invention aims to provide a simple and easy energy calibration method of a nuclear back flushing gas detector, which is used for energy calibration by combining an alpha source with a Monte Carlo simulation program.
In order to achieve the above purpose, the technical scheme adopted by the invention is a nuclear recoil method gas detector energy scale method, which comprises the following steps:
step S1, obtaining the ratio of the number of uranium isotope atomic nuclei in uranium materials used for plating targets; the uranium target plated with the uranium material is arranged in the gas detector;
S2, acquiring a first alpha spectrum, and confirming a channel address corresponding to a first counting peak value, wherein the first alpha spectrum refers to an alpha spectrum emitted by the uranium target in the gas detector, and the first counting peak value refers to a counting peak value in the first alpha spectrum; in the first alpha spectrum, Y-axis data is a count value, and X-axis data is a track address;
S3, obtaining a second alpha spectrum, and confirming the energy corresponding to a second counting peak value, wherein the second alpha spectrum is a simulated alpha spectrum of uranium target emission in the simulated gas detector obtained through a simulation program, and the second counting peak value is a counting peak value in the second alpha spectrum; in the second alpha spectrum, Y-axis data is a count value, and X-axis data is energy;
and S4, completing energy graduation of the gas detector through the channel address corresponding to the first counting peak value and the energy corresponding to the second counting peak value.
Further, in the step S1, a ratio of the number of uranium isotopes including U234, U235, U236, and U238 in the uranium material for plating a target is obtained by thermal ionization mass spectrometry using a thermal ionization mass spectrometer.
Further, in the step S3, uranium isotope emission alpha particle branching ratio information of the uranium material for plating a target, structural information of the gas detector, and information of the uranium target are brought into the simulation program for simulating the second alpha spectrum.
Further, in the step S3, the simulation program is a monte carlo simulation program.
Further, in the step S1, the method further includes the steps of plating the uranium target, assembling the gas detector, and filling hydrogen-containing gas for neutron recoil into the gas detector.
The invention has the beneficial effects that:
The energy information corresponding to the channel address of the peak position on the alpha particle pulse amplitude spectrum can be given out by combining an alpha source with a Monte Carlo simulation program, so that the energy scale of the nuclear back flushing gas detector measuring system is completed; the method does not need to adopt an accelerator to generate monoenergetic neutrons, and then carries out energy graduation by recoil of proton energy, thereby greatly reducing the requirements on laboratory conditions.
Drawings
FIG. 1 is a schematic illustration of a U-235 fission ionization chamber according to an embodiment of the present invention;
FIG. 2 is a first alpha spectrum as described in embodiments of the present invention;
FIG. 3 is a second alpha spectrum as described in embodiments of the present invention.
Detailed Description
The invention is further described below with reference to the drawings and examples.
The invention provides an energy scale method of a nuclear back flushing gas detector, which comprises the following steps:
Step S1, obtaining the ratio of the number of uranium isotope atomic nuclei in uranium materials used for plating targets; the uranium target plated with uranium substances is arranged in the gas detector;
S2, acquiring a first alpha spectrum, and confirming a channel address corresponding to a first counting peak value, wherein the first alpha spectrum refers to an alpha spectrum emitted by a uranium target in a gas detector, and the first counting peak value refers to a counting peak value in the first alpha spectrum; in the first alpha spectrum, Y-axis data is a count value, and X-axis data is a track address;
Step S3, obtaining a second alpha spectrum, and confirming the energy corresponding to a second counting peak value, wherein the second alpha spectrum refers to a simulated alpha spectrum of uranium target emission in a simulated gas detector obtained through a simulation program, and the second counting peak value refers to a counting peak value in the second alpha spectrum; in the second alpha spectrum, Y-axis data is count value, and X-axis data is energy;
and S4, completing the energy scale of the gas detector through the channel address corresponding to the first counting peak value and the energy corresponding to the second counting peak value.
In step S1, the ratio of the number of uranium isotopes including U234, U235, U236, and U238 in the uranium species used for plating the target is obtained by thermal ionization mass spectrometry using thermal ionization mass spectrometry.
In step S3, uranium isotope emission alpha particle branching ratio information of the uranium species used for the target plating, structural information of the gas detector, and information of the uranium target are brought into a simulation program for simulating the second alpha spectrum.
In step S3, the simulation program is a monte carlo simulation program.
In step S1, the method further comprises the steps of target plating the uranium target, assembling a gas detector, and filling hydrogen-containing gas for neutron recoil into the gas detector.
Examples
The following illustrates the actual operation of the energy calibration method of a nuclear back flush gas detector provided by the present invention. A U-235 fission ionization chamber is used as a gas detector, and the structure of the U-235 fission ionization chamber is shown in FIG. 1.
In FIG. 1, the U-235 fission ionization chambers are two back-to-back symmetrical sub-ionization chambers, wherein the main geometry of any sub-ionization chamber is that the shell is 1mm thick oxygen-free copper, the uranium target is 2.5cm in diameter and 161.67 mug/cm 2 in thickness, the substrate is platinum with 3.6cm in diameter and 0.3mm in thickness, and the collection electrode is 0.1mm thick oxygen-free copper. The interior was filled with 1.56E-3g/cm 3 of argon methane gas (Ar 90%, CH 4%).
Step S1, obtaining the ratio of the number of uranium isotope atomic nuclei in uranium materials used for plating targets by adopting a thermal ionization mass spectrometer through thermal ionization mass spectrometry (the result is shown in table 1), plating targets on the uranium targets after obtaining the ratio of the number of the uranium isotope atomic nuclei, assembling a U-235 fission ionization chamber, and filling hydrogen atom-containing gas used for neutron recoil.
TABLE 1 percentage of uranium isotopes
Isotope names The occupied portion/%
U234 1.262
U235 90.118
U236 0.2294
U238 8.390
Uranium isotope half-life information is shown in table 2:
TABLE 2 half-life of uranium isotopes
Isotope names Half-life/y
U234 2.455E+5
U235 7.04E+8
U236 2.342E+7
U238 4.468E+9
Uranium isotope emission alpha particle branching ratio information is shown in tables 3 and 4:
TABLE 3U-234, 235 transmit alpha branch ratio
TABLE 4U-236, 238 transmit alpha branch ratio
From tables 2 to 4, the relative intensities of alpha particles of different energies emitted per unit time can be deduced, and specific information is shown in Table 5:
TABLE 5 relative intensities of alpha particles of different energies
The alpha particles in Table 5 are not sorted by energy rise or fall, but are sorted by isotope, and it can be seen from Table 5 that the pulse amplitude spectrum (first alpha spectrum) obtained when the energy of alpha particles emitted by the uranium target is mainly 4.7224MeV and 4.7746MeV, and the U-235 fission ionization chamber is subjected to a high voltage of 500V is shown in FIG. 2.
Step S2, an alpha spectrum (a first alpha spectrum) emitted by a uranium target in the U-235 fission ionization chamber needs to be measured, and is shown in FIG. 2;
Step S3, as can be seen from FIG. 2, there is a very good peak, but the corresponding energy is obviously not 4.7746MeV, because the energy of alpha particles emitted by the uranium target cannot be completely deposited in the ionization chamber gas, if the energy scale is wanted to be performed on the measurement system, monte Carlo program simulation can be adopted to give the energy represented by the peak address, the alpha source adopted by Monte Carlo program simulation is various homonymous sources of the geometrical uranium target material, the energy information is as shown in Table 5, and the energy spectrum (second alpha spectrum) of the deposition of the alpha particles in the ionization chamber gas is as shown in FIG. 3;
In step S4, the trace address 205 at the peak (i.e., the first count peak) is known from fig. 2, and the energy 2.228MeV at the peak (i.e., the second count peak) is known from fig. 3, thus completing the energy scale of the nuclear back flush gas detector measurement system.
The device according to the invention is not limited to the examples described in the specific embodiments, and a person skilled in the art obtains other embodiments according to the technical solution of the invention, which also belong to the technical innovation scope of the invention.

Claims (5)

1. An energy scale method for a nuclear recoil method gas detector, comprising the following steps:
step S1, obtaining the ratio of the number of uranium isotope atomic nuclei in uranium materials used for plating targets; the uranium target plated with the uranium material is arranged in the gas detector;
S2, acquiring a first alpha spectrum, and confirming a channel address corresponding to a first counting peak value, wherein the first alpha spectrum refers to an alpha spectrum emitted by the uranium target in the gas detector, and the first counting peak value refers to a counting peak value in the first alpha spectrum; in the first alpha spectrum, Y-axis data is a count value, and X-axis data is a track address;
S3, obtaining a second alpha spectrum, and confirming the energy corresponding to a second counting peak value, wherein the second alpha spectrum is a simulated alpha spectrum of uranium target emission in the simulated gas detector obtained through a simulation program, and the second counting peak value is a counting peak value in the second alpha spectrum; in the second alpha spectrum, Y-axis data is a count value, and X-axis data is energy;
and S4, completing energy graduation of the gas detector through the channel address corresponding to the first counting peak value and the energy corresponding to the second counting peak value.
2. The nuclear recoil gas detector energy scaling method of claim 1, wherein: in the step S1, a ratio of the number of uranium isotopes including U234, U235, U236, and U238 in the uranium material for plating a target is obtained by thermal ionization mass spectrometry using a thermal ionization mass spectrometer.
3. The nuclear recoil gas detector energy scaling method of claim 1, wherein: in the step S3, the uranium isotope emission alpha particle branching ratio information of the uranium material for plating the target, the structural information of the gas detector, and the information of the uranium target are brought into the simulation program for simulating the second alpha spectrum.
4. The nuclear recoil gas detector energy scaling method of claim 1, wherein: in the step S3, the simulation program is a monte carlo simulation program.
5. The nuclear recoil gas detector energy scaling method of claim 1, wherein: in the step S1, the method further comprises the steps of plating the uranium target, assembling the gas detector, and filling hydrogen-containing gas for neutron recoil into the gas detector.
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