CN113866046B - Method for measuring surface density of thermal neutron absorption material - Google Patents
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- 238000000034 method Methods 0.000 title claims abstract description 36
- 239000000463 material Substances 0.000 title abstract description 24
- 238000010521 absorption reaction Methods 0.000 title description 4
- 238000002834 transmittance Methods 0.000 claims abstract description 40
- 239000011358 absorbing material Substances 0.000 claims abstract description 24
- 238000005259 measurement Methods 0.000 claims abstract description 20
- 238000004519 manufacturing process Methods 0.000 claims description 13
- 230000004907 flux Effects 0.000 claims description 10
- 230000005540 biological transmission Effects 0.000 claims description 9
- 238000012544 monitoring process Methods 0.000 claims description 8
- 238000004364 calculation method Methods 0.000 claims description 7
- 230000005855 radiation Effects 0.000 claims description 4
- 230000009897 systematic effect Effects 0.000 claims description 4
- 230000008859 change Effects 0.000 claims description 3
- 238000011161 development Methods 0.000 abstract description 4
- 238000001514 detection method Methods 0.000 abstract description 2
- 238000011160 research Methods 0.000 abstract description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 4
- 229910052796 boron Inorganic materials 0.000 description 4
- 238000004458 analytical method Methods 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- 238000001739 density measurement Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000013076 uncertainty analysis Methods 0.000 description 2
- 239000004698 Polyethylene Substances 0.000 description 1
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 230000005865 ionizing radiation Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- -1 polyethylene Polymers 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 229910052709 silver Inorganic materials 0.000 description 1
- 239000004332 silver Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N9/00—Investigating density or specific gravity of materials; Analysing materials by determining density or specific gravity
- G01N9/24—Investigating density or specific gravity of materials; Analysing materials by determining density or specific gravity by observing the transmission of wave or particle radiation through the material
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Abstract
The invention relates to a method for measuring the surface density of a thermal neutron absorbing material. By adopting the method provided by the invention, the functional relation between the transmittance of the thermal neutron absorbing material and the surface density is constructed by measuring the thermal neutron transmittance of a group of thermal neutron absorbing material standard samples with known surface densities, and the surface density of an unknown sample is calculated by utilizing the relation, so that the method for quickly and accurately measuring the surface density of the thermal neutron absorbing nuclide without damaging the physical structure of the sample is constructed. The method for nondestructively and rapidly measuring the surface density of the thermal neutron shielding material has the characteristics of simplicity in operation and reliability in data, can detect the uniformity of the surface density of the same material and the repeatability of the surface densities of different batches of materials, and provides data basis for research, development and use of the materials. Meanwhile, the method provided by the invention can realize rapid detection of the material, greatly shortens the measurement time, and is more suitable for industrial application.
Description
Technical Field
The invention belongs to the field of ionizing radiation metering, and relates to a method for measuring the surface density of a thermal neutron absorbing material.
Background
With the development of the nuclear industry, post-treatment plants and spent fuel storage devices store large amounts of spent fuel and radioactive waste. The accumulated spent fuel can release thermal neutrons, the thermal neutrons need to be shielded and wrapped, and the wrapping material needs to have thermal neutron absorption capacity and mechanical strength. The common thermal neutron absorbing materials comprise polyethylene, boron, cadmium, silver and other heavy metals, and are generally realized by adding low-cost natural boron into the common metal materials due to the large demand of shielding materials and high requirements on mechanical strength. The boron content is generally determined according to the shielding requirement and the absorption section calculation of thermal neutrons in the design stage, and errors possibly caused by the manufacturing method and the technical process are ignored in the mode; however, due to different manufacturing methods and processes, certain differences necessarily exist between the content of the thermal neutron absorbing nuclide and the design value, so that the content of the thermal neutron absorbing nuclide is essential to be measured. In addition, there are methods in the industry that intercept a section of material and give the content of nuclide components through chemical analysis, but since B-10 absorbs thermal neutrons, chemical analysis can only give the content of B, if the content of B-10 is estimated according to the abundance of natural boron, the deviation is too large and the result is inaccurate.
In the field of nuclear industry, the areal density of useful thermal neutron absorbing nuclides is an effective parameter for evaluating the shielding effectiveness of thermal neutron shielding materials. With the development of the nuclear industry, the demand of thermal neutron shielding materials is increased, and the traditional method cannot rapidly finish the surface density measurement of each material. Therefore, there is a need to develop a method for rapidly and accurately measuring the areal density of thermal neutron absorbing species of samples without destroying the physical structure of the samples, so as to be suitable for industrial applications.
Disclosure of Invention
Aiming at the defects existing in the prior art, the invention aims to provide a method for measuring the surface density of a thermal neutron absorbing material, which is used for constructing a functional relation between the transmittance and the surface density by measuring the transmittance of the thermal neutron absorbing material and calculating the surface density of an unknown sample by using the relation, so as to construct a method for quickly and accurately measuring the surface density of the thermal neutron absorbing nuclide of the sample without damaging the physical structure of the sample.
To achieve this object, the present invention provides a method of measuring the areal density of a thermal neutron absorbing material, the method comprising the steps of:
s1, measuring thermal neutron transmission flux and thermal neutron transmissivity of a group of standard samples with known surface densities, wherein the standard samples are numbered as natural numbers i from 1 to n, and the corresponding surface densities are Σ i Obtained byThe transmittance of corresponding thermal neutrons is marked as eta i ；
S2, measuring the transmissivity eta of the unknown sample k k ；
S3, calculating the surface density sigma of the unknown sample k k ；
S4, measuring errors and measuring uncertainty analysis.
Further, the method for measuring the thermal neutron transmission flux comprises the following steps: adopting the collimated thermal neutron beam to irradiate a standard sample i to be measured, and selecting a measuring point with a proper distance from the back surface of the thermal neutron beam irradiation surface of the standard sample i along the thermal neutron beam irradiation direction to measure the thermal neutron transmission flux; the cross-sectional area of the collimated thermal neutron beam is smaller than that of a sensitive area of a detector, and the detector is used for eliminating interference of scattered neutrons; the counting rate of the measuring points is 2-3 orders of magnitude higher than the background counting rate.
Further, the thermal neutron transmittance η of the standard sample i i Calculated using formula (1):
wherein,a background count rate for the absence of thermal neutron beam and without the placement of the standard sample i; />A background count rate for the standard sample i without thermal neutron beam; />A counting rate when the standard sample i is not placed and has a thermal neutron beam; />The counting rate is the counting rate when the standard sample i is placed and has a thermal neutron beam.
Further, the detector is placed at a measurement point 5cm from the surface of the standard sample i.
Further, the detector adopts BF 3 A counter or He-3 proportional counter.
Further, the thermal neutron transmittance η of the unknown sample k k The following formula was used for calculation:
wherein:the background counting rate is the background counting rate when no thermal neutron beam exists and no measured standard sample k is placed; />The background counting rate is the background counting rate when no thermal neutron beam exists and the tested standard sample k is placed; />Counting rate when the thermal neutron beam exists and the measured standard sample k is not placed; />Is the counting rate when the thermal neutron beam exists and the measured standard sample k is placed.
Further, a monitoring instrument is arranged to monitor the change of the radiation field value of the thermal neutron beam in real time, and the monitoring value measured by the monitoring instrument is recorded as
Further, if the thermal neutron transmittance η of the unknown sample k k Thermal neutron transmittance η between standard sample i i Thermal neutron transmittance η with standard sample i+1 i+1 Between, i.e. eta i ＜η k ＜η i+1 The areal density Σ of the unknown sample k k According to (2)And (3) calculating:
wherein eta i-1 Thermal neutron transmittance of the standard sample i-1; sigma and method for producing the same i-1 The surface density of the sample I-1 is the surface density of a standard sample; sigma and method for producing the same i+1 The areal density of the standard sample i+1;is the supervision value of the standard sample i; />Is the supervision value of the standard sample i-1; />Is the supervision value of the standard sample i+1.
Further, if the thermal neutron beam used is stable, the value is monitoredIs negligible; thermal neutron transmittance η of said unknown sample k k Thermal neutron transmittance η between standard sample i i Thermal neutron transmittance η with standard sample i+1 i+1 Between, i.e. eta i ＜η k ＜η i+1 When the surface density sigma of the unknown sample k k The calculation is performed according to formula (3):
wherein eta i-1 Thermal neutron transmittance of the standard sample i-1; sigma and method for producing the same i-1 The surface density of the sample I-1 is the surface density of a standard sample; sigma and method for producing the same i+1 The areal density of the standard sample i+1.
Further, the measurement errors mainly comprise systematic errors and random errors; the system errors comprise errors caused by a measuring device, errors caused by thermal neutron beam stability and errors of the surface density nominal value of a standard sample; the randomness error mainly comprises an error introduced by measurement repeatability, a sample placement error and an error introduced by a detector position;
the measurement uncertainty mainly comprises uncertainty of introduction of statistical fluctuation, uncertainty of an area density value of a standard sample and uncertainty of introduction of a measurement system.
The method for measuring the surface density of the thermal neutron absorbing material has the beneficial effects that the method for measuring the surface density of the thermal neutron absorbing material provided by the invention is adopted, a functional relation between the transmittance of the thermal neutron absorbing material and the surface density is constructed by measuring the thermal neutron transmittance of a group of thermal neutron absorbing material standard samples with known surface densities, and the surface density of an unknown sample is calculated by utilizing the relation, so that the method for quickly and accurately measuring the surface density of the thermal neutron absorbing nuclide without damaging the physical structure of the sample is constructed. The method for nondestructively and rapidly measuring the surface density of the thermal neutron shielding material has the characteristics of simplicity in operation and reliability in data, can detect the uniformity of the surface density of the same material and the repeatability of the surface densities of different batches of materials, and provides data basis for research, development and use of the materials. Meanwhile, the demand of the nuclear industry field for thermal neutron shielding materials is increasing, the surface density measurement of each material cannot be completed rapidly by the traditional method, and the method provided by the invention can realize rapid detection of the materials, greatly shortens the measurement time and is more suitable for industrial application.
Drawings
FIG. 1 is a flow chart of a method for measuring the surface density of a thermal neutron absorbing material according to the present invention.
Detailed Description
The invention is further described below with reference to the drawings and detailed description.
A method of measuring the areal density of a thermal neutron absorbing material comprising the steps of:
s1, measuring thermal neutron transmission flux and transmittance of a group of standard samples with known surface densities, wherein the standard samples are numbered 1,2,3, … i and … n, and the corresponding surface densities are sequentially Σ 1 ,Σ 2 ,Σ 3 ,…Σ i ,…Σ n The corresponding thermal neutron transmittance is measured and sequentially recorded as eta 1 ,η 2 ,η 3 ,…η i ,…η n 。
The experimental method for measuring the thermal neutron transmission flux comprises the following steps: the collimated thermal neutron beam is adopted to irradiate a standard sample i to be measured, a measuring point with proper distance from the back surface of the thermal neutron beam irradiation surface of the standard sample i is selected along the thermal neutron beam irradiation direction, and a detector is placed, wherein the counting rate at the position of the measuring point is generally required to be 2-3 orders of magnitude higher than the background counting rate. In this embodiment, the detector is placed at a distance of 5cm from the surface of the standard sample i to be measured to measure the thermal neutron transmission flux. The cross-sectional area of the collimated thermal neutron beam is required to be smaller than that of the sensitive area of the detector, and the detector is required to be well shielded to eliminate the interference of scattered neutrons. The detector is selected to have a sufficiently large thermal neutron response to distinguish between background count after shielding and count rate due to transmitted neutrons, generally using BF 3 A counter or He-3 proportional counter. If testing is performed on a radiation field with larger flux fluctuation, a monitoring instrument needs to be arranged, the change of the radiation field value is monitored in real time, and the reading of the monitoring instrument is recorded as
(1) Measuring the background count rate without thermal neutron beam and without placing the standard sample i to be measured, and recording as
(2) Measuring the background count rate of the standard sample i without thermal neutron beam and placed, and recording as
(3) The counting rate when the thermal neutron beam is measured and the measured standard sample i is not placed is recorded as
(4) Measuring the counting rate of the thermal neutron beam when the measured standard sample i is placed, and marking as
Thermal neutron transmittance η of a standard sample i being measured i Can be calculated by using the formula (1):
s2, measuring the transmissivity eta of the unknown sample k k According to the experimental method described in the step S1, the background count rate without thermal neutron beam and without the measured standard sample k is measured and recorded asMeasuring the background count rate of the standard sample k without thermal neutron beam and placed therein, and marking the background count rate as +.>The count rate when the thermal neutron beam is measured and the measured standard sample k is not placed is marked +.>The counting rate of the sample k with thermal neutron beam and placed as the standard sample is marked +.>The thermal neutron transmittance η of the unknown sample k at this time k Can be expressed as:
s3, calculating the surface density sigma of the unknown sample k k : if the thermal neutron transmittance eta of the unknown sample k k Thermal neutron transmittance η between standard sample i i With standard sample i +Thermal neutron transmittance η of 1 i+1 Between, i.e. eta i ＜η k ＜η i+1 The areal density Σ of the unknown sample k k The calculation can be performed according to formula (2):
wherein eta is i-1 Thermal neutron transmittance of the standard sample i-1; sigma and method for producing the same i-1 The surface density of the sample I-1 is the surface density of a standard sample; sigma and method for producing the same i+1 The areal density of the standard sample i+1;is the supervision value of the standard sample i; />Is the supervision value of the standard sample i-1; />Is the supervision value of the standard sample i+1.
If the thermal neutron beam used is very stable, as if the thermal neutron field is generated after the neutron source is slowed down, the value is monitoredThe variation is small and negligible, and the formula (2) can be simplified into the formula (3):
s4, measurement error and measurement uncertainty analysis: analysis according to equation (2) shows that the measurement error is mainly composed of systematic error and randomness error. The systematic errors include errors caused by a measuring device, errors caused by thermal neutron beam stability, errors of the nominal value of the surface density of the standard sample, and the like. The randomness error mainly comprises errors introduced by measurement repeatability, errors introduced by sample placement and detector positions, and the like.
The measurement uncertainty mainly comprises uncertainty of introduction of statistical fluctuation, uncertainty of an area density value of a standard sample, uncertainty of introduction of a measurement system and the like.
In the field of nuclear industry, thermal neutron transmittance of thermal neutron shielding materials is commonly used to evaluate the shielding effect, and the surface density of useful thermal neutron absorbing nuclides is an effective parameter for evaluating the shielding effect of thermal neutron shielding materials. According to the embodiment of the invention, the thermal neutron transmittance of a group of thermal neutron absorbing material standard samples with known surface densities is measured, a functional relation between the thermal neutron absorbing material transmittance and the surface densities is constructed, and the surface densities of unknown samples are calculated by using the functional relation, so that a method for quickly and accurately measuring the surface densities of thermal neutron absorbing nuclides of the thermal neutron absorbing material standard samples without damaging the physical structures of the samples is constructed.
For a material containing only one thermal neutron absorbing nuclide, the result measured by the method provided by the invention is the surface density of the thermal neutron absorbing nuclide contained in the thermal neutron absorbing material; if the method provided by the invention is used for measuring materials containing various thermal neutron absorbing nuclides, the measured result is the surface density equivalent value of the thermal neutron absorbing nuclides contained in the thermal neutron absorbing materials.
The above embodiments are merely illustrative of the present invention and various modifications and variations may be made thereto by those skilled in the art without departing from the spirit and scope of the present invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (6)
1. A method of measuring the areal density of a thermal neutron absorbing material, the method comprising the steps of:
s1, measuring thermal neutron transmission flux and thermal neutron transmissivity of a group of standard samples with known surface densities, wherein the standard samples are numbered as natural numbers i from 1 to n, and the corresponding surface densities are Σ i The obtained corresponding thermal neutron transmittance is marked as eta i ；
S2、Measuring the transmittance η of an unknown sample k k ；
S3, calculating the surface density sigma of the unknown sample k k ；
S4, analyzing measurement errors and measurement uncertainty;
setting a monitoring instrument to monitor the change of the radiation field value of the thermal neutron beam in real time, wherein the monitoring value measured by the monitoring instrument is recorded as
If the thermal neutron transmittance eta of the unknown sample k k Thermal neutron transmittance η between standard sample i i Thermal neutron transmittance η with standard sample i+1 i+1 Between, i.e. eta i ＜η k ＜η i+1 The areal density Σ of the unknown sample k k The calculation is performed according to formula (2):
wherein eta i-1 Thermal neutron transmittance of the standard sample i-1; sigma and method for producing the same i-1 The surface density of the sample I-1 is the surface density of a standard sample; sigma and method for producing the same i+1 The areal density of the standard sample i+1;is the supervision value of the standard sample i; />Is the supervision value of the standard sample i-1; />A supervision value of the standard sample i+1;
thermal neutron transmittance η of said standard sample i i Calculated using formula (1):
wherein,a background count rate for the absence of thermal neutron beam and without the placement of the standard sample i; />A background count rate for the standard sample i without thermal neutron beam; />A counting rate when the standard sample i is not placed and has a thermal neutron beam; />A counting rate when the standard sample i is placed and is provided with a thermal neutron beam;
thermal neutron transmittance η of said unknown sample k k The following formula was used for calculation:
wherein:the background counting rate is the background counting rate when no thermal neutron beam exists and no measured standard sample k is placed; />The background counting rate is the background counting rate when no thermal neutron beam exists and the tested standard sample k is placed; />Counting rate when the thermal neutron beam exists and the measured standard sample k is not placed; />Is the counting rate when the thermal neutron beam exists and the measured standard sample k is placed.
2. The method for measuring the surface density of the thermal neutron absorbing material according to claim 1, wherein the method for measuring the thermal neutron transmission flux comprises the following steps: adopting the collimated thermal neutron beam to irradiate a standard sample i to be measured, and selecting a measuring point with a proper distance from the back surface of the thermal neutron beam irradiation surface of the standard sample i along the thermal neutron beam irradiation direction to measure the thermal neutron transmission flux; the cross-sectional area of the collimated thermal neutron beam is smaller than that of a sensitive area of a detector, and the detector is used for eliminating interference of scattered neutrons; the counting rate of the measuring points is 2-3 orders of magnitude higher than the background counting rate.
3. A method of measuring the areal density of a thermal neutron absorbing material according to claim 2, wherein the detector is placed at a measurement point 5cm from the surface of the standard sample i.
4. The method of measuring the areal density of a thermal neutron absorbing material according to claim 2, wherein the detector employs BF 3 A counter or He-3 proportional counter.
5. A method for measuring the areal density of a thermal neutron absorbing material according to claim 1, wherein if the thermal neutron beam used is stable, then the value is monitoredIs negligible; thermal neutron transmittance η of said unknown sample k k Thermal neutron transmittance η between standard sample i i Thermal neutron transmittance η with standard sample i+1 i+1 Between, i.e. eta i ＜η k ＜η i+1 When the surface density of the unknown sample k isΣ k The calculation is performed according to formula (3):
wherein eta i-1 Thermal neutron transmittance of the standard sample i-1; sigma and method for producing the same i-1 The surface density of the sample I-1 is the surface density of a standard sample; sigma and method for producing the same i+1 The areal density of the standard sample i+1.
6. The method of claim 5, wherein the measurement errors include mainly systematic errors and random errors; the system errors comprise errors caused by a measuring device, errors caused by thermal neutron beam stability and errors of the surface density nominal value of a standard sample; the randomness error mainly comprises an error introduced by measurement repeatability, a sample placement error and an error introduced by a detector position;
the measurement uncertainty mainly comprises uncertainty of introduction of statistical fluctuation, uncertainty of an area density value of a standard sample and uncertainty of introduction of a measurement system.
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